JEFF-3.1 Evaluated Data Library Project

JEFF-3.1, References to evaluations, MF1, MT451

Below follows the complete description of proton data evaluations for JEFF-3.1 in isotope order:

Isotope	Evaluation	MAT #
20-Ca- 40	Description	2025
20-Ca- 42	Description	2031
20-Ca- 43	Description	2034
20-Ca- 44	Description	2037
20-Ca- 46	Description	2043
20-Ca- 48	Description	2049
21-Sc- 45	Description	2125
22-Ti- 46	Description	2225
22-Ti- 47	Description	2228
22-Ti- 48	Description	2231
22-Ti- 49	Description	2234
22-Ti- 50	Description	2237
26-Fe- 54	Description	2625
26-Fe- 56	Description	2631
26-Fe- 57	Description	2634
26-Fe- 58	Description	2637
32-Ge- 70	Description	3225
32-Ge- 72	Description	3231
32-Ge- 73	Description	3234
32-Ge- 74	Description	3237
32-Ge- 76	Description	3243
82-Pb-204	Description	8225
82-Pb-206	Description	8231
82-Pb-207	Description	8234
82-Pb-208	Description	8237
83-Bi-209	Description	8325

Description from the evaluators:

==================================================================

20-Ca- 40 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 2025 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Ca-40

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Ca-40, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Ca-40, DWBA was used to compute the direct
cross sections to several low-lying discrete levels:

Level Energy Spin/Parity Deformation length delta_L

2 3.736690 3.0- 1.340
3 3.904380 2.0+ 0.360
4 4.491430 5.0- 0.930
+ a few additional states with small deformation parameters.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Tables 8-9 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Ca-40, an adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions of a
factor of 0.7 was done to predict the emission spectra.
Experiments for proton induced reaction spectra for

- Sc-45 : 65 MeV [sak80]
- Ca-48 : 25, 35 and 45 MeV [bla76]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[bla76] M. Blann, R.R. Doering, A. Galonsky, D.M. Patterson, and
F.E. Serr, Nucl. Phys. A257, 15 (1976).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[sak80] H. Sakai, K. Hosono, N. Matsuoka, S. Nagamachi, K. Okada,
K. Maeda, and H. Shimizu, Nucl. Phys. A344, 41 (1980).

************************* C O N T E N T S ************************

==================================================================

20-Ca- 42 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 2031 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Ca-42

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Ca-42, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Ca-42, DWBA was used to compute the direct
cross sections to several low-lying discrete levels:

Level Energy Spin/Parity Deformation parameter beta_l

1 1.524730 2.0+ 0.247
9 3.446960 3.0- 0.303
+ a few additional states with small deformation parameters.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Tables 8-9 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Ca-42, an adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions of a
factor of 0.7 was done to predict the emission spectra.
Experiments for proton induced reaction spectra for

- Sc-45 : 65 MeV [sak80]
- Ca-48 : 25, 35 and 45 MeV [bla76]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[bla76] M. Blann, R.R. Doering, A. Galonsky, D.M. Patterson, and
F.E. Serr, Nucl. Phys. A257, 15 (1976).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[sak80] H. Sakai, K. Hosono, N. Matsuoka, S. Nagamachi, K. Okada,
K. Maeda, and H. Shimizu, Nucl. Phys. A344, 41 (1980).

************************* C O N T E N T S ************************

==================================================================

20-Ca- 43 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 2034 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Ca-43

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Ca-43, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Ca-43, DWBA was used to compute the direct
cross sections to several low-lying discrete levels of the
even-even core Ca-42. The weak-coupling model was then used
to spread the collective strength over the odd levels of Ca-43.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Tables 8-9 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Ca-43, an adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions of a
factor of 0.7 was done to predict the emission spectra.
Experiments for proton induced reaction spectra for

- Sc-45 : 65 MeV [sak80]
- Ca-48 : 25, 35 and 45 MeV [bla76]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[bla76] M. Blann, R.R. Doering, A. Galonsky, D.M. Patterson, and
F.E. Serr, Nucl. Phys. A257, 15 (1976).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[sak80] H. Sakai, K. Hosono, N. Matsuoka, S. Nagamachi, K. Okada,
K. Maeda, and H. Shimizu, Nucl. Phys. A344, 41 (1980).

************************* C O N T E N T S ************************

==================================================================

20-Ca- 44 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 2037 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Ca-44

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Ca-44, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Ca-44, DWBA was used to compute the direct
cross sections to several low-lying discrete levels:

Level Energy Spin/Parity Deformation parameter beta_L

1 1.157050 2.0+ 0.253
8 3.307860 3.0- 0.240
+ a few additional states with small deformation parameters.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Tables 8-9 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Ca-44, an adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions of a
factor of 0.7 was done to predict the emission spectra.
Experiments for proton induced reaction spectra for

- Sc-45 : 65 MeV [sak80]
- Ca-48 : 25, 35 and 45 MeV [bla76]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[bla76] M. Blann, R.R. Doering, A. Galonsky, D.M. Patterson, and
F.E. Serr, Nucl. Phys. A257, 15 (1976).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[sak80] H. Sakai, K. Hosono, N. Matsuoka, S. Nagamachi, K. Okada,
K. Maeda, and H. Shimizu, Nucl. Phys. A344, 41 (1980).

************************* C O N T E N T S ************************

==================================================================

20-Ca- 46 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 2043 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Ca-46

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Ca-46, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Ca-46, DWBA was used to compute the direct
cross sections to several low-lying discrete levels:

Level Energy Spin/Parity Deformation parameter beta_l

1 1.346000 2.0+ 0.153
6 3.614000 3.0- 0.204
+ a few additional states with small deformation parameters.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Tables 8-9 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Ca-46, an adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions of a
factor of 0.7 was done to predict the emission spectra.
Experiments for proton induced reaction spectra for

- Sc-45 : 65 MeV [sak80]
- Ca-48 : 25, 35 and 45 MeV [bla76]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[bla76] M. Blann, R.R. Doering, A. Galonsky, D.M. Patterson, and
F.E. Serr, Nucl. Phys. A257, 15 (1976).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[sak80] H. Sakai, K. Hosono, N. Matsuoka, S. Nagamachi, K. Okada,
K. Maeda, and H. Shimizu, Nucl. Phys. A344, 41 (1980).

************************* C O N T E N T S ************************

==================================================================

20-Ca- 48 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 2049 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Ca-48

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Ca-48, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Ca-48, DWBA was used to compute the direct
cross sections to several low-lying discrete levels:

Level Energy Spin/Parity Deformation parameter beta_l

1 3.831720 2.0+ 0.106
4 4.506960 3.0- 0.230
+ a few additional states with small deformation parameters.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Tables 8-9 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Ca-48, an adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions of a
factor of 0.7 was done to predict the emission spectra.
Experiments for proton induced reaction spectra for

- Sc-45 : 65 MeV [sak80]
- Ca-48 : 25, 35 and 45 MeV [bla76]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[bla76] M. Blann, R.R. Doering, A. Galonsky, D.M. Patterson, and
F.E. Serr, Nucl. Phys. A257, 15 (1976).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[sak80] H. Sakai, K. Hosono, N. Matsuoka, S. Nagamachi, K. Okada,
K. Maeda, and H. Shimizu, Nucl. Phys. A344, 41 (1980).

************************* C O N T E N T S ************************

==================================================================

21-Sc- 45 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 2125 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Sc-45

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Sc-45, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Sc-45, DWBA was used to compute the direct
cross sections to several low-lying discrete levels of the
even-even core Ca-44. The weak-coupling model was then used
to spread the collective strength over the odd levels of Sc-45.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Tables 8-9 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Sc-45, an adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions of a
factor of 0.7 was done to predict the emission spectra.
Experiments for proton induced reaction spectra for

- Sc-45 : 65 MeV [sak80]
- Ca-48 : 25, 35 and 45 MeV [bla76]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[bla76] M. Blann, R.R. Doering, A. Galonsky, D.M. Patterson, and
F.E. Serr, Nucl. Phys. A257, 15 (1976).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[sak80] H. Sakai, K. Hosono, N. Matsuoka, S. Nagamachi, K. Okada,
K. Maeda, and H. Shimizu, Nucl. Phys. A344, 41 (1980).

************************* C O N T E N T S ************************

==================================================================

22-Ti- 46 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 2225 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Ti-46

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Ti-46, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Ti-46, DWBA was used to compute the direct
cross sections to several low-lying discrete levels:

Level Energy Spin/Parity Deformation parameter beta_l

1 0.889286 2.0+ 0.317
2 2.009850 4.0+ 0.100
5 3.058600 3.0- 0.142
+ a few additional states with small deformation parameters.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Tables 8-9 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Ti-46, an adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions of a
factor of 0.7 was done to predict the emission spectra.
Experiments for proton induced reaction spectra for

- Sc-45 : 65 MeV [sak80]
- Ca-48 : 25, 35 and 45 MeV [bla76]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[bla76] M. Blann, R.R. Doering, A. Galonsky, D.M. Patterson, and
F.E. Serr, Nucl. Phys. A257, 15 (1976).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[sak80] H. Sakai, K. Hosono, N. Matsuoka, S. Nagamachi, K. Okada,
K. Maeda, and H. Shimizu, Nucl. Phys. A344, 41 (1980).

************************* C O N T E N T S ************************

==================================================================

22-Ti- 47 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 2228 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Ti-47

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Ti-47, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Ti-47, DWBA was used to compute the direct
cross sections to several low-lying discrete levels of the
even-even core Ti-46. The weak-coupling model was then used
to spread the collective strength over the odd levels of Ti-47.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Tables 8-9 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Ti-47, an adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions of a
factor of 0.7 was done to predict the emission spectra.
Experiments for proton induced reaction spectra for

- Sc-45 : 65 MeV [sak80]
- Ca-48 : 25, 35 and 45 MeV [bla76]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[bla76] M. Blann, R.R. Doering, A. Galonsky, D.M. Patterson, and
F.E. Serr, Nucl. Phys. A257, 15 (1976).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[sak80] H. Sakai, K. Hosono, N. Matsuoka, S. Nagamachi, K. Okada,
K. Maeda, and H. Shimizu, Nucl. Phys. A344, 41 (1980).

************************* C O N T E N T S ************************

==================================================================

22-Ti- 48 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 2231 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Ti-48

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Ti-48, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Ti-48, DWBA was used to compute the direct
cross sections to several low-lying discrete levels:

Level Energy Spin/Parity Deformation parameter beta_l

1 0.983519 2.0+ 0.269
2 2.295630 4.0+ 0.150
10 3.358800 3.0- 0.197
+ a few additional states with small deformation parameters.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Tables 8-9 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Ti-48, an adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions of a
factor of 0.7 was done to predict the emission spectra.
Experiments for proton induced reaction spectra for

- Sc-45 : 65 MeV [sak80]
- Ca-48 : 25, 35 and 45 MeV [bla76]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[bla76] M. Blann, R.R. Doering, A. Galonsky, D.M. Patterson, and
F.E. Serr, Nucl. Phys. A257, 15 (1976).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[sak80] H. Sakai, K. Hosono, N. Matsuoka, S. Nagamachi, K. Okada,
K. Maeda, and H. Shimizu, Nucl. Phys. A344, 41 (1980).

************************* C O N T E N T S ************************

==================================================================

22-Ti- 49 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 2234 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Ti-49

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Ti-49, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Ti-49, DWBA was used to compute the direct
cross sections to several low-lying discrete levels of the
even-even core Ti-48. The weak-coupling model was then used
to spread the collective strength over the odd levels of Ti-49.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Tables 8-9 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Ti-49, an adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions of a
factor of 0.7 was done to predict the emission spectra.
Experiments for proton induced reaction spectra for

- Sc-45 : 65 MeV [sak80]
- Ca-48 : 25, 35 and 45 MeV [bla76]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[bla76] M. Blann, R.R. Doering, A. Galonsky, D.M. Patterson, and
F.E. Serr, Nucl. Phys. A257, 15 (1976).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[sak80] H. Sakai, K. Hosono, N. Matsuoka, S. Nagamachi, K. Okada,
K. Maeda, and H. Shimizu, Nucl. Phys. A344, 41 (1980).

************************* C O N T E N T S ************************

==================================================================

22-Ti- 50 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 2237 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Ti-50

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Ti-50, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Ti-50, DWBA was used to compute the direct
cross sections to several low-lying discrete levels:

Level Energy Spin/Parity Deformation length delta_l

1 1.553780 2.0+ 0.340
2 2.674910 4.0+ 0.400
12 4.409990 3.0- 0.660
+ a few additional states with small deformation parameters.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Tables 8-9 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Ti-50, an adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions of a
factor of 0.7 was done to predict the emission spectra.
Experiments for proton induced reaction spectra for

- Sc-45 : 65 MeV [sak80]
- Ca-48 : 25, 35 and 45 MeV [bla76]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[bla76] M. Blann, R.R. Doering, A. Galonsky, D.M. Patterson, and
F.E. Serr, Nucl. Phys. A257, 15 (1976).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[sak80] H. Sakai, K. Hosono, N. Matsuoka, S. Nagamachi, K. Okada,
K. Maeda, and H. Shimizu, Nucl. Phys. A344, 41 (1980).

************************* C O N T E N T S ************************

==================================================================

26-Fe- 54 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 2625 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Fe-54

Author: A.J. Koning and M.C. Duijvestijn, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten, HINDAS collaboration

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Fe-54, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Fe-54, DWBA was used to compute the direct
cross sections to several low-lying discrete levels:

Level Energy Spin/Parity Deformation length delta_L

1 1.408190 2.0+ 0.87000
2 2.538100 4.0+ 0.31000
3 2.561300 0.0+ 0.31000
5 2.959000 2.0+ 0.49000
6 3.166000 2.0+ 0.24000
7 3.294800 4.0+ 0.22000
11 3.833200 4.0+ 0.37000
14 4.047800 4.0+ 0.14000
18 4.267800 4.0+ 0.31000
19 4.290800 0.0+ 0.15000
20 4.578500 2.0+ 0.17000

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file. Examples are the (p,xp)....(p,xa)
spectra for Fe-nat and the (n,xp)....(n,xa) spectra for Fe-nat.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Tables 8-9 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### INELASTIC CROSS SECTIONS

For inelastic scattering to the first excited state, the
calculations have been tested against two sets of
available measurements [ecc66,bou92], The agreement is very good.

##### OTHER PARTIAL CROSS SECTIONS

- (p,a):

The calculation follows closely the data from [lev91] up to
20 MeV. Above this energy it starts to underpredict the data.

##### PARTICLE SPECTRA

For Fe-54 two parameters in the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions had to
be adjusted. The asymptotical value for matrix element at high
energies is multiplied by a factor of 0.4 and the constant for
the energy shift is multiplied by 0.8, to describe the emission
spectra.
Various experiments for proton induced reaction spectra for

- Fe-54 : 26 MeV [wat97], 29, 39 and 62 MeV [ber73]
- Fe-56 : 22 MeV [bir80], 14 and 26 MeV [wat97],
14 MeV [spr73], 62 MeV [ber73]
- Fe-nat : 113 MeV [mei89]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[ber73] F.E. Bertrand and R.W. Peelle, Phys. Rev. C8, 1045
(1973).
[bir80] N.S. Birjukov, B.V. Zhuravlev, A.P. Rudenko,
O.A. Salnikov, and V.I. Trykova, Yadernaya Fizika 31,
561 (1980).
[bou92] N.Boukharouba,C.E.Brient,S.M.Grimes,V.Mishra,
R.S.Pedroni, Phys. Rev. C46,2375 (1992)
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[ecc66] S.F.Eccles,H.F.Lutz,V.A.Madsen, Phys. Rev. 141,1067 (1966)
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[lev91] V.N.Levkovskij,"Act.Cs.By Protons and Alphas",Moscow
(1991)
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[mei89] M.M. Meier, D.A. Clark, C.A. Goulding, J.B. McClelland,
G.L. Morgan, C.E. Moss, and W.B. Amian, Nucl. Sci. Eng.
102, 310 (1989).
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[spr73] A. Sprinzak, A.J. Kennedy, J.C. Pacer, J. Wiley, and
N.T. Porile, Nucl. Phys. A203, 280 (1973).
[wat97] Y. Watanabe, S. Yoshioka, M. Harada, K. Sato, Y. Nakao,
H. Ijiri, S. Chiba, T. Fukahori, S. Meigo, O. Iwamoto,
and N. Koori, in Proceedings of the International
Conference on Nuclear Data for Science and Technology,
Trieste, Italy, edited by G. Reffo (1997), p. 580.

************************* C O N T E N T S ************************

==================================================================

26-Fe- 56 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 2631 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Fe-56

Author: A.J. Koning and M.C. Duijvestijn, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten, HINDAS collaboration

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Fe-56, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Fe-56, DWBA was used to compute the direct
cross sections to several low-lying discrete levels:

Level Energy Spin/Parity Deformation parameter beta_L

1 0.846776 2.0+ 0.23900
2 2.085080 4.0+ 0.02200
3 2.657560 2.0+ 0.04500
5 2.959920 2.0+ 0.01500
8 3.122930 4.0+ 0.06500
9 3.369740 2.0+ 0.04500
10 3.388490 6.0+ 0.02800
14 3.602000 2.0+ 0.03800
17 3.755620 6.0+ 0.03000
19 3.832000 2.0+ 0.02300

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file. Examples are the (p,xp)....(p,xa)
spectra for Fe-nat and the (n,xp)....(n,xa) spectra for Fe-nat.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Tables 8-9 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### INELASTIC CROSS SECTIONS

For inelastic scattering to the first excited state, the
calculations have been tested against four sets of
available measurements [ecc66,bou92,cha74,dye81].
The agreement is very good. Only the data point from [ecc66] is
underestimated by 30%.


##### OTHER PARTIAL CROSS SECTIONS

- (p,g):

The calculated capture cross section is based on the default
renormalization to the s-wave strength function, to the available
experimental data, all taken from the EXFOR database
[wen93,kri77,dra73,bou92].

- (p,n):

Many experimental data points are found in EXFOR. The calculation
closely describes the data from [jen70,gad74,ant85,tan59].

- (p,2n):

Changing the level density parameter at the binding energy in the
daughter nucleus by -10% resulted in a nice fit of the one data
point at 21.5 MeV [coh55] and an overprediction of
[lag79,jen70,lev91].

- (p,np):

Fitting the level density parameter at the binding energy in the
daughter nucleus (-10%) yields an agreement between the
calculation and data from [jen70] within 15%.

- (p,na):

The calculated peak lies at 26 MeV, which is lower than the
experimental data indicate (>30 MeV). Even after changing level
density parameters by -30% the calculation still overpredicts the
data [lev91] with a factor of 2.

- (p,n2p):

The calculation vyer nicely follows the measurement of [jen70].

##### PARTICLE SPECTRA

For Fe-56 two parameters in the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions had to
be adjusted. The asymptotical value for matrix element at high
energies is multiplied by a factor of 0.3 and the constant for
the energy shift is multiplied by 0.48, to describe the emission
spectra.
Various experiments for proton induced reaction spectra for

- Fe-54 : 26 MeV [wat97], 29, 39 and 62 MeV [ber73]
- Fe-56 : 22 MeV [bir80], 14 and 26 MeV [wat97],
14 MeV [spr73], 62 MeV [ber73]
- Fe-nat : 113 MeV [mei89]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[ant85] A.E.Antropov,P.P.Zarubin,YU.A.Aleksandrov,I.YU.Gorshkov,
35.Conf.Nucl.Spectr.and Nucl.Struct.,Leningrad,369 (1985)
[ber73] F.E. Bertrand and R.W. Peelle, Phys. Rev. C8, 1045
(1973).
[bir80] N.S. Birjukov, B.V. Zhuravlev, A.P. Rudenko,
O.A. Salnikov, and V.I. Trykova, Yadernaya Fizika 31,
561 (1980).
[bou92] N.Boukharouba,C.E.Brient,S.M.Grimes,V.Mishra,
R.S.Pedroni, Phys. Rev. C46,2375 (1992)
[cha74] C.C.Chang,N.S.Wall,Z.Fraenkel, Phys. Rev. Lett. 33,
1493 (1974)
[coh55] B.L.Cohen, E.Newman, Phys. Rev. 99,718 (1955)
[dra73] D.M.Drake,S.L.Whetstone,I.Halpern,NPA 203,257 (1973)
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[dye81] P.Dyer,D.Bodansky,A.G.Seamster,E.B.Norman, D.R.Maxson,
Phys. Rev C23,1865 (1981)
[ecc66] S.F.Eccles,H.F.Lutz,V.A.Madsen, Phys. Rev. 141,1067
(1966)
[gad74] E.Gadioli, A.M.Grassi Strini, G.LO Bianco, G.Strini,
G.Tagliaferri, Nuovo Cimento A22,547 (1974)
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[jen70] I.L.Jenkins, A.G.Wainj,Journal of Inorganic and Nuclear
Chemistry 32, 1419 (1970)
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[kri77] G.A.Krivonosov,O.I.Ekhichev,B.A.Nemashkalo,V.E.Storizhko,
V.K.Chirt,Izv. Rossiiskoi Akademii Nauk,
Ser. Fiz,41, (10), 2196 (1977)
[lag79] M.C.Lagunas-Solar,J.A.Jungerman,Applied Radiation and
Isotopes 30, 25 (1979)
[lev91] V.N.Levkovskij,"Act.Cs.By Protons and Alphas",Moscow
(1991)
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[mei89] M.M. Meier, D.A. Clark, C.A. Goulding, J.B. McClelland,
G.L. Morgan, C.E. Moss, and W.B. Amian, Nucl. Sci. Eng.
102, 310 (1989).
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[spr73] A. Sprinzak, A.J. Kennedy, J.C. Pacer, J. Wiley, and
N.T. Porile, Nucl. Phys. A203, 280 (1973).
[tan59] S.Tanaka, M.Furakawa,Journal of the Physical Society of
Japan 14, 1269 (1959)
[wat97] Y. Watanabe, S. Yoshioka, M. Harada, K. Sato, Y. Nakao,
H. Ijiri, S. Chiba, T. Fukahori, S. Meigo, O. Iwamoto,
and N. Koori, in Proceedings of the International
Conference on Nuclear Data for Science and Technology,
Trieste, Italy, edited by G. Reffo (1997), p. 580.
[wen93] Z. Wenrong,L. Hanlin,Y. Weixiang, Chinese J.
of Nuclear Physics 15, (4),337 (1993)

************************* C O N T E N T S ************************

==================================================================

26-Fe- 57 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 2634 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Fe-57

Author: A.J. Koning and M.C. Duijvestijn, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Fe-57, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Fe-57, DWBA was used to compute the direct
cross sections to several low-lying discrete levels of the
even-even core Fe-56. The weak-coupling model was then used
to spread the collective strength over the odd levels of Fe-57.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file. Examples are the (p,xp)....(p,xa)
spectra for Fe-nat and the (n,xp)....(n,xa) spectra for Fe-nat.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Table 11 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### OTHER PARTIAL CROSS SECTIONS

- (p,n):

Raising the level density parameter at the binding energy of 57Co
by 13% yields a calculation that fits the (p,n)-data
[lev91,joh60,kol91].

- (p,a):

In order to fit the available experimental data [lev91], the
level density parameter at the binding energy of the daughter
nucleus was increased by 15%. The peak is nicely reproduced, but
the rise and fall of the calculated excitation function are too
steep.

- (p,2n):

No fitting was done to describe the (p,2n)-data [lev91], the peak
is underestimated somewhat by 10% and shifted by 3 MeV to lower
energies.

- (p,2p):

Without any tuning, the calculation closely follows the
experimental data [lev91].

- (p,3n):

No fitting was needed to describe the experimental data [lev91].

##### PARTICLE SPECTRA

For Fe-57 two parameters in the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions had to
be adjusted. The asymptotical value for matrix element at high
energies is multiplied by a factor of 0.3 and the constant for
the energy shift is multiplied by 0.48, to describe the emission
spectra.
Various experiments for proton induced reaction spectra for

- Fe-54 : 26 MeV [wat97], 29, 39 and 62 MeV [ber73]
- Fe-56 : 22 MeV [bir80], 14 and 26 MeV [wat97],
14 MeV [spr73], 62 MeV [ber73]
- Fe-nat : 113 MeV [mei89]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[ber73] F.E. Bertrand and R.W. Peelle, Phys. Rev. C8, 1045
(1973).
[bir80] N.S. Birjukov, B.V. Zhuravlev, A.P. Rudenko,
O.A. Salnikov, and V.I. Trykova, Yadernaya Fizika 31,
561 (1980).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[joh60] C.H.Johnson, A.Galonsky, C.N.Iinskeep,Rep. ORNL-2910,25
(1960)
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kol91] A.A.Kolozhvari,V.P.Gusev,A.B.Smirnov,A.E.Antropov,
P.P.Zarubin, Izv. Rossiiskoi Akademii Nauk, Ser.Fiz. 55,
168 (1991)
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[lev91] V.N.Levkovskij,"Act.Cs.By Protons and Alphas",Moscow
(1991)
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[mei89] M.M. Meier, D.A. Clark, C.A. Goulding, J.B. McClelland,
G.L. Morgan, C.E. Moss, and W.B. Amian, Nucl. Sci. Eng.
102, 310 (1989).
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[spr73] A. Sprinzak, A.J. Kennedy, J.C. Pacer, J. Wiley, and
N.T. Porile, Nucl. Phys. A203, 280 (1973).
[wat97] Y. Watanabe, S. Yoshioka, M. Harada, K. Sato, Y. Nakao,
H. Ijiri, S. Chiba, T. Fukahori, S. Meigo, O. Iwamoto,
and N. Koori, in Proceedings of the International
Conference on Nuclear Data for Science and Technology,
Trieste, Italy, edited by G. Reffo (1997), p. 580.

************************* C O N T E N T S ************************

==================================================================

26-Fe- 58 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 2637 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Fe-58

Author: A.J. Koning and M.C. Duijvestijn, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Fe-58, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Fe-58, DWBA was used to compute the direct
cross sections to several low-lying discrete levels:

Level Energy Spin/Parity Deformation parameter beta_L

1 0.810784 2.0+ 0.87000
12 3.135000 4.0+ 0.09000
24 3.860800 3.0- 0.18950
+ a few additional states with small deformation parameters.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file. Examples are the (p,xp)....(p,xa)
spectra for Fe-nat and the (n,xp)....(n,xa) spectra for Fe-nat.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Table 11 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### OTHER PARTIAL CROSS SECTIONS

- (p,n):

The level density parameter at the binding energy of the daughter
nucleus was increased by 10% to fit the available experimental
data [lev91,zar90].

- (p,2n):

Raising the level density parameter at the binding energy of 57Co
by 13% yields a calculation that fits the (p,2n)-data [lev91].

- (p,3n):

No fitting was needed to describe the experimental data [lev91].

- (p,na):

In order to fit the (p,a)-data on 57Fe [lev91], the level density
parameter at the binding energy of the daughter nucleus was
increased by 15%. This results in a calculation that
underestimates the (p,na)-data on 58Fe [lev91] in the peak
by 30%.

##### PARTICLE SPECTRA

For Fe-58 two parameters in the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions had to
be adjusted. The asymptotical value for matrix element at high
energies is multiplied by a factor of 0.3 and the constant for
the energy shift is multiplied by 0.48, to describe the emission
spectra.
Various experiments for proton induced reaction spectra for

- Fe-54 : 26 MeV [wat97], 29, 39 and 62 MeV [ber73]
- Fe-56 : 22 MeV [bir80], 14 and 26 MeV [wat97],
14 MeV [spr73], 62 MeV [ber73]
- Fe-nat : 113 MeV [mei89]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[ber73] F.E. Bertrand and R.W. Peelle, Phys. Rev. C8, 1045
(1973).
[bir80] N.S. Birjukov, B.V. Zhuravlev, A.P. Rudenko,
O.A. Salnikov, and V.I. Trykova, Yadernaya Fizika 31,
561 (1980).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[lev91] V.N.Levkovskij,"Act.Cs.By Protons and Alphas",Moscow
(1991)
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[mei89] M.M. Meier, D.A. Clark, C.A. Goulding, J.B. McClelland,
G.L. Morgan, C.E. Moss, and W.B. Amian, Nucl. Sci. Eng.
102, 310 (1989).
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[spr73] A. Sprinzak, A.J. Kennedy, J.C. Pacer, J. Wiley, and
N.T. Porile, Nucl. Phys. A203, 280 (1973).
[wat97] Y. Watanabe, S. Yoshioka, M. Harada, K. Sato, Y. Nakao,
H. Ijiri, S. Chiba, T. Fukahori, S. Meigo, O. Iwamoto,
and N. Koori, in Proceedings of the International
Conference on Nuclear Data for Science and Technology,
Trieste, Italy, edited by G. Reffo (1997), p. 580.
[zar90] P.P.Zarubin,N.N.Aby Issa,A.V.Smirnov,A.E.Antropov,
Izv. Rossiiskoi Akademii Nauk, Ser.Fiz. 54,104 (1990)

************************* C O N T E N T S ************************

==================================================================

32-Ge- 70 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 3225 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Ge-70

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Ge-70, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Ge-70, a harmonic vibrational
coupled-channels calculation was performed to compute the
direct cross sections to several low-lying one-phonon and
two-phonon discrete levels:

Level Energy Spin/Parity Deformation parameter beta_l

1 1.039250 2.0+ 0.225 (L=2) 1-phonon
2 1.215410 0.0+ 2-phonon
3 1.707900 2.0+ 2-phonon
4 2.153500 4.0+ 2-phonon
9 3.446960 3.0- 0.274 (L=3) 1-phonon
+ a few additional states with small deformation parameters.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Table 11 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Ge-70, an adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions of a
factor of 1.2 was done to predict the emission spectra,
analoguous to the calculation for neutrons.
Experiments for proton induced reaction spectra do not exist
for Ge-isotopes. The closest nuclides for which spectral
information exists are Cu and Y-Zr. Our global exciton model
analysis, however, has enabled us to constrain the results,
through the aforementioned matrix element, for particle yields
and double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).

************************* C O N T E N T S ************************

==================================================================

32-Ge- 72 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 3231 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Ge-72

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Ge-72, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Ge-72, a harmonic vibrational
coupled-channels calculation was performed to compute the
direct cross sections to several low-lying one-phonon and
two-phonon discrete levels:

Level Energy Spin/Parity Deformation parameter beta_l

2 0.834011 2.0+ 0.242 (L=2) 1-phonon
3 1.463990 0.0+ 2-phonon
4 1.728300 2.0+ 2-phonon
5 2.029000 4.0+ 2-phonon
12 2.514790 3.0- 0.264 (L=3) 1-phonon
+ a few additional states with small deformation parameters.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Table 11 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Ge-72, an adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions of a
factor of 1.2 was done to predict the emission spectra,
analoguous to the calculation for neutrons.
Experiments for proton induced reaction spectra do not exist
for Ge-isotopes. The closest nuclides for which spectral
information exists are Cu and Y-Zr. Our global exciton model
analysis, however, has enabled us to constrain the results,
through the aforementioned matrix element, for particle yields
and double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).

************************* C O N T E N T S ************************

==================================================================

32-Ge- 73 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 3234 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Ge-73

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Ge-73, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Ge-73, a harmonic vibrational
coupled-channels calculation was performed to compute the
direct cross sections to several low-lying one-phonon and
two-phonon discrete levels of the even-even core Ge-72. The
weak-coupling model was then used to spread the collective
strength over the odd levels of Ge-73.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Table 11 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Ge-73, an adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions of a
factor of 1.2 was done to predict the emission spectra,
analoguous to the calculation for neutrons.
Experiments for proton induced reaction spectra do not exist
for Ge-isotopes. The closest nuclides for which spectral
information exists are Cu and Y-Zr. Our global exciton model
analysis, however, has enabled us to constrain the results,
through the aforementioned matrix element, for particle yields
and double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).

************************* C O N T E N T S ************************

==================================================================

32-Ge- 74 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 3237 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Ge-74

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Ge-74, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Ge-74, a harmonic vibrational
coupled-channels calculation was performed to compute the
direct cross sections to several low-lying one-phonon and
two-phonon discrete levels:

Level Energy Spin/Parity Deformation parameter beta_l

1 0.595850 2.0+ 0.283 (L=2) 1-phonon
2 1.204200 0.0+ 2-phonon
3 1.463760 2.0+ 2-phonon
4 1.482810 4.0+ 2-phonon
14 2.536310 3.0- 0.145 (L=3) 1-phonon
+ a few additional states with small deformation parameters.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Table 11 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Ge-74, an adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions of a
factor of 1.2 was done to predict the emission spectra,
analoguous to the calculation for neutrons.
Experiments for proton induced reaction spectra do not exist
for Ge-isotopes. The closest nuclides for which spectral
information exists are Cu and Y-Zr. Our global exciton model
analysis, however, has enabled us to constrain the results,
through the aforementioned matrix element, for particle yields
and double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).

************************* C O N T E N T S ************************

==================================================================

32-Ge- 76 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 3243 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Ge-76

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Ge-76, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Ge-76, a harmonic vibrational
coupled-channels calculation was performed to compute the
direct cross sections to several low-lying one-phonon and
two-phonon discrete levels:

Level Energy Spin/Parity Deformation parameter beta_l

1 0.562930 2.0+ 0.262 (L=2) 1-phonon
2 1.108440 0.0+ 2-phonon
3 1.410080 2.0+ 2-phonon
5 1.911070 4.0+ 2-phonon
16 2.692400 3.0- 0.144 (L=3) 1-phonon
+ a few additional states with small deformation parameters.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Table 11 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Ge-76, an adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions of a
factor of 1.2 was done to predict the emission spectra,
analoguous to the calculation for neutrons.
Experiments for proton induced reaction spectra do not exist
for Ge-isotopes. The closest nuclides for which spectral
information exists are Cu and Y-Zr. Our global exciton model
analysis, however, has enabled us to constrain the results,
through the aforementioned matrix element, for particle yields
and double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).

************************* C O N T E N T S ************************

==================================================================

82-Pb-204 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 8225 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Pb-204

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Pb-204, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Pb-204, DWBA was used to compute the direct
cross sections to several low-lying discrete levels:

Level Energy Spin/Parity Deformation parameter beta_L

1 0.899171 2.0+ 0.039
44 2.627350 5.0+ 0.088
+ a few additional states with small deformation parameters.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file. Examples are the (p,xp)....(p,xa)
spectra for Pb-nat and the (n,xn) excitation functions up to
200 MeV for Bi-209.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Table 11 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Pb-204, no adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions was
needed, to describe the emission spectra.
Various experiments for proton induced reaction spectra for

- Pb204-Pb208: 11 MeV [bir87], 25 MeV [har87]
- Pb208 : 25, 35 and 45 MeV [bla76], 80 MeV [tra89],
120 and 160 MeV [sco90]
- Pb-nat : 63 MeV [mar63], 113 MeV [mei89]
- Bi-209 : 39 and 62 MeV [ber73], 65 MeV [sak80],
90 MeV [kal83,wu90]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[ber73] F.E. Bertrand and R.W. Peelle, Phys. Rev. C8, 1045
(1973).
[bir87] N.S. Birjukov, B.V. Zhuravlev, A.P. Rudenko, and V.I.
Trykova, 37th All-Union Conf. on Nuclear Spectroscopy and
Nuclear Structure, Jurmala, USSR 1987, p. 284 (1987).
[bla76] M. Blann, R.R. Doering, A. Galonsky, D.M. Patterson, and
F.E. Serr, Nucl. Phys. A257, 15 (1976).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[har87] K. Harder, A. Kaminsky, E. Mordhorst, W. Scobel, and M.
Trabandt, Phys. Rev. C36, 834 (1987).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal83] A.M. Kalend, B.D. Anderson, A.R. Baldwin, R. Madey, J.W.
Watson, C.C. Chang, H.D. Holmgren, R.W. Koontz, J.R. Wu,
and H. Machner, Phys. Rev. C28, 105 (1983).
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[mar03] N. Marie-Nourry, in Workshop on Nuclear Data for the
Transmutation of Nuclear Waste, 2003, GSI-Darmstadt,
Germany (2003).
[mei89] M.M. Meier, D.A. Clark, C.A. Goulding, J.B. McClelland,
G.L. Morgan, C.E. Moss, and W.B. Amian, Nucl. Sci. Eng.
102, 310 (1989).
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[sak80] H. Sakai, K. Hosono, N. Matsuoka, S. Nagamachi, K. Okada,
K. Maeda, and H. Shimizu, Nucl. Phys. A344, 41 (1980).
[sco90] W. Scobel, M. Trabandt, M. Blann, B. A. Pohl,
B. A. Remington, R. C. Byrd, C. C. Foster, R. Bonetti,
C. Chiesa, and S. M. Grimes, Phys. Rev. C41, 2010 (1990).
[tra89] M. Trabandt, W. Scobel, M. Blann, B.A. Pohl, R.C. Byrd,
C.C. Foster, R. Bonetti, and S.M. Grimes, Phys. Rev. C39,
452 (1989).
[wu79] J.R. Wu, C.C. Chang, and H.D. Holmgren, Phys. Rev. C19,
698 (1979).

************************* C O N T E N T S ************************

==================================================================

82-Pb-206 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 8231 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Pb-206

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Pb-206, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Pb-206, DWBA was used to compute the direct
cross sections to several low-lying discrete levels:

Level Energy Spin/Parity Deformation length delta_L

1 0.803100 2.0+ 0.212
5 1.684040 4.0+ 0.160
17 2.647840 3.0- 0.738
+ a few additional states with small deformation parameters.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file. Examples are the (p,xp)....(p,xa)
spectra for Pb-nat and the (n,xn) excitation functions up to
200 MeV for Bi-209.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Table 11 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Pb-206, no adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions was
needed, to describe the emission spectra.
Various experiments for proton induced reaction spectra for

- Pb204-Pb208: 11 MeV [bir87], 25 MeV [har87]
- Pb208 : 25, 35 and 45 MeV [bla76], 80 MeV [tra89],
120 and 160 MeV [sco90]
- Pb-nat : 63 MeV [mar63], 113 MeV [mei89]
- Bi-209 : 39 and 62 MeV [ber73], 65 MeV [sak80],
90 MeV [kal83,wu90]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[ber73] F.E. Bertrand and R.W. Peelle, Phys. Rev. C8, 1045
(1973).
[bir87] N.S. Birjukov, B.V. Zhuravlev, A.P. Rudenko, and V.I.
Trykova, 37th All-Union Conf. on Nuclear Spectroscopy and
Nuclear Structure, Jurmala, USSR 1987, p. 284 (1987).
[bla76] M. Blann, R.R. Doering, A. Galonsky, D.M. Patterson, and
F.E. Serr, Nucl. Phys. A257, 15 (1976).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[har87] K. Harder, A. Kaminsky, E. Mordhorst, W. Scobel, and M.
Trabandt, Phys. Rev. C36, 834 (1987).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal83] A.M. Kalend, B.D. Anderson, A.R. Baldwin, R. Madey, J.W.
Watson, C.C. Chang, H.D. Holmgren, R.W. Koontz, J.R. Wu,
and H. Machner, Phys. Rev. C28, 105 (1983).
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[mar03] N. Marie-Nourry, in Workshop on Nuclear Data for the
Transmutation of Nuclear Waste, 2003, GSI-Darmstadt,
Germany (2003).
[mei89] M.M. Meier, D.A. Clark, C.A. Goulding, J.B. McClelland,
G.L. Morgan, C.E. Moss, and W.B. Amian, Nucl. Sci. Eng.
102, 310 (1989).
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[sak80] H. Sakai, K. Hosono, N. Matsuoka, S. Nagamachi, K. Okada,
K. Maeda, and H. Shimizu, Nucl. Phys. A344, 41 (1980).
[sco90] W. Scobel, M. Trabandt, M. Blann, B. A. Pohl,
B. A. Remington, R. C. Byrd, C. C. Foster, R. Bonetti,
C. Chiesa, and S. M. Grimes, Phys. Rev. C41, 2010 (1990).
[tra89] M. Trabandt, W. Scobel, M. Blann, B.A. Pohl, R.C. Byrd,
C.C. Foster, R. Bonetti, and S.M. Grimes, Phys. Rev. C39,
452 (1989).
[wu79] J.R. Wu, C.C. Chang, and H.D. Holmgren, Phys. Rev. C19,
698 (1979).

************************* C O N T E N T S ************************

==================================================================

82-Pb-207 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 8234 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Pb-207

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Pb-207, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Pb-207, DWBA was used to compute the direct
cross sections to several low-lying discrete levels of the
even-even core Pb-208. The weak-coupling model was then used
to spread the collective strength over the odd levels of Pb-207.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file. Examples are the (p,xp)....(p,xa)
spectra for Pb-nat and the (n,xn) excitation functions up to
200 MeV for Bi-209.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Table 11 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Pb-207, no adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions was
needed, to describe the emission spectra.
Various experiments for proton induced reaction spectra for

- Pb204-Pb208: 11 MeV [bir87], 25 MeV [har87]
- Pb208 : 25, 35 and 45 MeV [bla76], 80 MeV [tra89],
120 and 160 MeV [sco90]
- Pb-nat : 63 MeV [mar63], 113 MeV [mei89]
- Bi-209 : 39 and 62 MeV [ber73], 65 MeV [sak80],
90 MeV [kal83,wu90]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[ber73] F.E. Bertrand and R.W. Peelle, Phys. Rev. C8, 1045
(1973).
[bir87] N.S. Birjukov, B.V. Zhuravlev, A.P. Rudenko, and V.I.
Trykova, 37th All-Union Conf. on Nuclear Spectroscopy and
Nuclear Structure, Jurmala, USSR 1987, p. 284 (1987).
[bla76] M. Blann, R.R. Doering, A. Galonsky, D.M. Patterson, and
F.E. Serr, Nucl. Phys. A257, 15 (1976).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[har87] K. Harder, A. Kaminsky, E. Mordhorst, W. Scobel, and M.
Trabandt, Phys. Rev. C36, 834 (1987).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal83] A.M. Kalend, B.D. Anderson, A.R. Baldwin, R. Madey, J.W.
Watson, C.C. Chang, H.D. Holmgren, R.W. Koontz, J.R. Wu,
and H. Machner, Phys. Rev. C28, 105 (1983).
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[mar03] N. Marie-Nourry, in Workshop on Nuclear Data for the
Transmutation of Nuclear Waste, 2003, GSI-Darmstadt,
Germany (2003).
[mei89] M.M. Meier, D.A. Clark, C.A. Goulding, J.B. McClelland,
G.L. Morgan, C.E. Moss, and W.B. Amian, Nucl. Sci. Eng.
102, 310 (1989).
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[sak80] H. Sakai, K. Hosono, N. Matsuoka, S. Nagamachi, K. Okada,
K. Maeda, and H. Shimizu, Nucl. Phys. A344, 41 (1980).
[sco90] W. Scobel, M. Trabandt, M. Blann, B. A. Pohl,
B. A. Remington, R. C. Byrd, C. C. Foster, R. Bonetti,
C. Chiesa, and S. M. Grimes, Phys. Rev. C41, 2010 (1990).
[tra89] M. Trabandt, W. Scobel, M. Blann, B.A. Pohl, R.C. Byrd,
C.C. Foster, R. Bonetti, and S.M. Grimes, Phys. Rev. C39,
452 (1989).
[wu79] J.R. Wu, C.C. Chang, and H.D. Holmgren, Phys. Rev. C19,
698 (1979).

************************* C O N T E N T S ************************

==================================================================

82-Pb-208 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 8237 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Pb-208

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten, HINDAS collaboration

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Pb-208, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Pb-208, DWBA was used to compute the direct
cross sections to several low-lying discrete levels:

Level Energy Spin/Parity Deformation parameter beta_L

1 2.614550 3.0- 0.120
2 3.197740 5.0- 0.064
4 3.708440 5.0- 0.034
7 3.960960 5.0- 0.018
9 4.037000 7.0- 0.038
11 4.050500 3.0- 0.013
12 4.085400 2.0+ 0.058
+ a few additional states with small deformation parameters.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file. Examples are the (n,xp)....(n,xa)
spectra for Pb-nat and the (n,xn) excitation functions up to
200 MeV for Bi-209.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Tables 8-9 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Pb-208, no adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions was
needed, to describe the emission spectra.
Various experiments for proton induced reaction spectra for

- Pb204-Pb208: 11 MeV [bir87], 25 MeV [har87]
- Pb208 : 25, 35 and 45 MeV [bla76], 80 MeV [tra89],
120 and 160 MeV [sco90]
- Pb-nat : 63 MeV [mar63], 113 MeV [mei89]
- Bi-209 : 39 and 62 MeV [ber73], 65 MeV [sak80],
90 MeV [kal83,wu90]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[ber73] F.E. Bertrand and R.W. Peelle, Phys. Rev. C8, 1045
(1973).
[bir87] N.S. Birjukov, B.V. Zhuravlev, A.P. Rudenko, and V.I.
Trykova, 37th All-Union Conf. on Nuclear Spectroscopy and
Nuclear Structure, Jurmala, USSR 1987, p. 284 (1987).
[bla76] M. Blann, R.R. Doering, A. Galonsky, D.M. Patterson, and
F.E. Serr, Nucl. Phys. A257, 15 (1976).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[har87] K. Harder, A. Kaminsky, E. Mordhorst, W. Scobel, and M.
Trabandt, Phys. Rev. C36, 834 (1987).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal83] A.M. Kalend, B.D. Anderson, A.R. Baldwin, R. Madey, J.W.
Watson, C.C. Chang, H.D. Holmgren, R.W. Koontz, J.R. Wu,
and H. Machner, Phys. Rev. C28, 105 (1983).
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[mar03] N. Marie-Nourry, in Workshop on Nuclear Data for the
Transmutation of Nuclear Waste, 2003, GSI-Darmstadt,
Germany (2003).
[mei89] M.M. Meier, D.A. Clark, C.A. Goulding, J.B. McClelland,
G.L. Morgan, C.E. Moss, and W.B. Amian, Nucl. Sci. Eng.
102, 310 (1989).
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[sak80] H. Sakai, K. Hosono, N. Matsuoka, S. Nagamachi, K. Okada,
K. Maeda, and H. Shimizu, Nucl. Phys. A344, 41 (1980).
[sco90] W. Scobel, M. Trabandt, M. Blann, B. A. Pohl,
B. A. Remington, R. C. Byrd, C. C. Foster, R. Bonetti,
C. Chiesa, and S. M. Grimes, Phys. Rev. C41, 2010 (1990).
[tra89] M. Trabandt, W. Scobel, M. Blann, B.A. Pohl, R.C. Byrd,
C.C. Foster, R. Bonetti, and S.M. Grimes, Phys. Rev. C39,
452 (1989).
[wu79] J.R. Wu, C.C. Chang, and H.D. Holmgren, Phys. Rev. C19,
698 (1979).

************************* C O N T E N T S ************************

==================================================================

83-Bi-209 NRG EVAL-OCT04 A.J. Koning
NRG-2004 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 Material 8325 REVISION 1
-----Incident proton data
------ENDF-6 Format
***************************** JEFF-3.1 *************************
** **
** Original data taken from: New evaluation **
** **
******************************************************************

NRG-2004: p + Bi-209

Author: A.J. Koning, NRG Petten

************** G E N E R A L I N F O R M A T I O N *************

This evaluated data file is based primarily on a theoretical
analysis with the nuclear model code TALYS [kon04], version 0.56.
The nuclear model parameters of TALYS have been adjusted to
reproduce the existing experimental data. The resulting data file
provides a complete representation of nuclear data needed for
transport, damage, heating, radioactivity, and shielding
applications over the incident proton energy range from
1 to 200 MeV.

This file is part of a larger collection of isotopic evaluations,
all created by running TALYS with input parameters that do not or
slightly deviate from the default values. The mutual quality of
these isotopic evaluations is thus relatively consistent.
The same set of nuclear models is used and, equally important,
the same ENDF-6 formatting procedures for each isotope. We have
intended to make this evaluation complete in its description of
reaction channels, and use a compact method to store the data.

All transport data for particles, photons and residual nuclides
are filed using a combination of MF1,3 and MF6. This includes
cross sections, angular distributions, double-differential
spectra, photon production cross sections, and residual
production (activation) cross sections. This evaluation can thus
be used as both transport and activation library.
The data file has been created automatically using the ENDF-6
format generator TEFAL.

##### ORIGIN

Data < 200 MeV : New evaluation NRG Petten

All data : Produced with TALYS code

*************************** T H E O R Y **************************

TALYS is a computer code system for the prediction and analysis
of nuclear reactions. TALYS simulates reactions that involve
neutrons, gamma-rays, protons, deuterons, tritons, helions and
alpha-particles, in the 1 keV - 200 MeV energy range and for
target nuclides of mass 12 and heavier. This is achieved by
implementing a suite of nuclear reaction models into a single
code system. It enables to evaluate nuclear reactions from
the unresolved resonance region up to intermediate energies. This
evaluation is based on a theoretical analysis that utilizes the
optical model, compound nucleus statistical theory, direct
reactions and pre-equilibrium processes, in combination with
databases and models for nuclear structure. For Bi-209, the
following output of TALYS is stored in this data file:

- Elastic and non-elastic cross sections
- Elastic scattering angular distributions
- Total particle cross sections, e.g. (p,xn), (p,xp),..
- Total particle energy spectra
- Total particle double-differential spectra
- Residual production cross sections

Here follows a short description of the used nuclear models:

##### OPTICAL MODEL

All optical model calculations are performed by ECIS-97 [ray94],
in TALYS used as a subroutine. The default optical model
potentials (OMP) used are the local and global parameterizations
of Koning and Delaroche [kon03]. These are phenomenological OMPs
for neutrons and protons which in principle are valid over the
1 keV - 200 MeV energy range. Solving the Schroedinger equation
with this OMP yields the total cross section, the shape-elastic
cross section, the shape-elastic angular distribution, the wave
functions for the direct reaction cross sections (see below), the
transmission coefficients for the compound nucleus model (see
below) and the reaction cross sections for the pre-equilibrium
model (see below).
For neutrons and protons, the used parameterization is given in
Eq. (7) of [kon03].
To calculate the transmission coefficients and reaction cross
sections for deuterons, tritons, helions and alpha particles, we
use OMPs that are directly derived from our nucleon potentials
using Watanabe's folding approach [mad88].

##### DIRECT REACTIONS

The built-in ECIS-97 is used for coupled-channels or DWBA
calculations for rotational or vibrational (or a combination of
these) nuclides. For Bi-209, DWBA was used to compute the direct
cross sections to several low-lying discrete levels of the
even-even core Pb-208. The weak-coupling model was then used
to spread the collective strength over the odd levels of Bi-209.

For proton libraries, the discrete inelastic cross sections are
spread over the continuum with a Gaussian distribution.

In addition, a macroscopic, phenomenological model to describe
giant resonances in the inelastic channel is used. For each
multipolarity an energy weighted sum rule applies and a DWBA
calculation with ECIS-97 is performed for each giant resonance
state. The cross section is then spread over the continuum with a
Gaussian distribution.

##### COMPOUND NUCLEUS

For compound nucleus reactions we use the Hauser-Feshbach model
[hau52]. The transmission coefficients have been generated with
the aforementioned OMPs and the full j,l-dependence of the
transmission coefficients in the Hauser-Feshbach model is used.
For each nucleus that can be reached, several discrete levels and
a continuum described by level densities are included
simultaneously as competing channels. Multiple compound emission
is continued until all reaction channels are closed and the
population distribution of all residual nuclides is depleted,
through gamma decay, until they end up in the ground state or in
an isomer.

For the level density, we take the composite formula proposed by
Gilbert and Cameron [gil65], consisting of a constant temperature
law at low energies and a Fermi gas expression at high energies.
For the level density parameter a we use the energy dependent
expression proposed by Ignatyuk [ign75] to take into account the
damping of shell effects at high excitation energy. We have
obtained the parameters for the Ignatyuk formula from a
simultaneous fit to all experimental D_0 values as present in the
RIPL library. If necessary, we adjust individual parameters to
obtain a better fit to experiment.

Gamma-ray transmission coefficients are generated with the
Kopecky-Uhl generalized Lorentzian for strength
functions [kop90], with giant dipole resonance parameters taken
from the RIPL library [rip98], and normalized with experimental
radiative widths [gar84].

##### PRE-EQUILIBRIUM REACTIONS

For pre-equilibrium reactions, which become important for
incident energies above about 10 MeV, we use the two-component
exciton model [kon04b], in which the neutron or proton types of
particles and holes are followed throughout the reaction. For
energies above 20 MeV, multiple pre-equilibrium emission up to
any order of particle emission was included in the calculations.
A parameterization for the squared matrix element is used that is
valid for the whole energy range of this evaluation.

For deuterons, tritons, helions and alpha-particles, an extra
contribution was added from the pick/up and knock-out reaction
model by Kalbach [kal01].

For photons, the model of Akkermans and Gruppelaar [akk85] was
applied, to simulate the direct and semi-direct capture
processes.

The angular distribution systematics by Kalbach [kal88] were used
to describe the angular distributions for all continuum
particles. An isotopic distribution for photons was adopted.

****** C O M P A R I S O N W I T H E X P E R I M E N T *****

This evaluation was performed simultaneously with other adjacent
isotopes, both for incident neutrons and protons. This enables,
when compared with a single-isotope effort, to put stronger
constraints on the produced calculated data, i.e. a globally
good comparison between TALYS and experimental data is requested
for all isotopes at the same time, while nucleus-specific input
(default or adjusted) parameters are consistently used for all
isotopes. Also, experimental data that is not available for the
isotope under study may be present, and tested, for adjacent
nuclides or for other projectiles. If these can be successfully
described by the models, a similar performance can be expected
for the present data file. Examples are the (p,xp)....(p,xa)
spectra for Pb-nat and the (n,xn) excitation functions up to
200 MeV for Bi-209.

##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING

The spherical OMP was tested against available experimental data.
The used parameters are those of Tables 8-9 of [kon03].
Consult [kon03] for the complete experimental database of elastic
scattering angular distributions and for a comparison of
calculations and measurements over the whole energy range.

##### PARTICLE SPECTRA

For Bi-209, no adjustment of the default matrix element
parameterization of [kon04b] for pre-equilibrium reactions was
needed, to describe the emission spectra.
Various experiments for proton induced reaction spectra for

- Pb204-Pb208: 11 MeV [bir87], 25 MeV [har87]
- Pb208 : 25, 35 and 45 MeV [bla76], 80 MeV [tra89],
120 and 160 MeV [sco90]
- Pb-nat : 63 MeV [mar63], 113 MeV [mei89]
- Bi-209 : 39 and 62 MeV [ber73], 65 MeV [sak80],
90 MeV [kal83,wu90]

have enabled us to better constrain the results, through
the aforementioned matrix element, for particle yields and
double-differential spectra for all ejectiles up to alpha
particles.

***************** F I L E I N F O R M A T I O N ****************

##### MF1: GENERAL INFORMATION

- MT451 : Descriptive data and directory

This text and the full directory of used MF/MT sections.

##### MF3: REACTION CROSS SECTIONS

- MT2 : Elastic scattering cross section: nuclear +
interference terms

Obtained by integrating the "nuclear-plus-interference" angular
distributions of MF=6. Note that because of the interference
effect, the tabulations in both MF=6 and MF=3 can be negative at
some energies and angles.

- MT5 : (p,anything) cross section

MT5 contains the total non-elastic cross section, with which the
information of MF6/MT5 can be combined to obtain particle
production cross sections and (double-)differential cross
sections.

##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS

In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and photon production
cross sections. All data are generated with TALYS.

- MT2 : Elastic scattering angular distribution: nuclear +
interference terms

Relative angular distributions are tabulated on an angular grid.
They are obtained by using the "nuclear-plus-interference" option
in MF=6, which corresponds to LAW=5, LTP=12, and the appropriate
integrated cross section is stored in MF=3. Note that because
of the interference effect, the tabulations in both MF=6 and
MF=3 can be negative at some energies and angles.

- MT5 : (p,anything) yields and energy-angle distributions

MT5 contains the production yields of particles and residual
products. It also contains the secondary energy-angle
distributions for all particles and photons. First, the yields
for neutrons are given for the whole energy range. Next, on a
secondary energy grid the relative emission spectra are given
together with the parameters for the Kalbach systematics for
angular distributions. Inelastic scattering cross sections for
discrete states have been broadened and added to the continuum
spectra. This procedure is repeated for protons, deuterons,
tritons, Helium-3, alpha particles and photons. Finally, the
residual production yields are given per final product. All these
yields and relative distributions can be multiplied with the
cross sections given in MF3/MT5 to get the production cross
sections and (double-)differential cross sections.

***** F I L E C H E C K I N G A N D P R O C E S S I N G ****

This file has been checked successfully by the BNL checking
codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has
been processed successfully into an MCNP library by the
processing code NJOY99.81 [mac00].

*********************** R E F E R E N C E S **********************

[akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95
(1985).
[ber73] F.E. Bertrand and R.W. Peelle, Phys. Rev. C8, 1045
(1973).
[bir87] N.S. Birjukov, B.V. Zhuravlev, A.P. Rudenko, and V.I.
Trykova, 37th All-Union Conf. on Nuclear Spectroscopy and
Nuclear Structure, Jurmala, USSR 1987, p. 284 (1987).
[bla76] M. Blann, R.R. Doering, A. Galonsky, D.M. Patterson, and
F.E. Serr, Nucl. Phys. A257, 15 (1976).
[dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001).
[gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA
Series on Neutron Physics and Nuclear Data in Science and
Technology, eds. A. Michaudon et al., p. 62 (1984).
[gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446
(1965).
[har87] K. Harder, A. Kaminsky, E. Mordhorst, W. Scobel, and M.
Trabandt, Phys. Rev. C36, 834 (1987).
[hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952).
[ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J.
[kal83] A.M. Kalend, B.D. Anderson, A.R. Baldwin, R. Madey, J.W.
Watson, C.C. Chang, H.D. Holmgren, R.W. Koontz, J.R. Wu,
and H. Machner, Phys. Rev. C28, 105 (1983).
[kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988).
[kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium
code with direct reactions, Duke University 2001,
www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/.
[kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231
(2003).
[kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished
(2004).
[kon04b] A.J. Koning and M.C. Duijvestijn, to be published
(2004).
[kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990).
[mac00] R.E. Macfarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on
Preequilibrium Reactions, Semmering, Austria,
February 10-12 1988, (OECD, Paris 1988), p. 103.
[mar03] N. Marie-Nourry, in Workshop on Nuclear Data for the
Transmutation of Nuclear Waste, 2003, GSI-Darmstadt,
Germany (2003).
[mei89] M.M. Meier, D.A. Clark, C.A. Goulding, J.B. McClelland,
G.L. Morgan, C.E. Moss, and W.B. Amian, Nucl. Sci. Eng.
102, 310 (1989).
[ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report
No. CEA-N-2772, 1994.
Nucl. Phys. 21, no. 3, 255 (1975).
[rip98] Handbook for calculations of nuclear reaction data:
Reference Input Parameter Library, IAEA-TECDOC-1034
(1998).
[sak80] H. Sakai, K. Hosono, N. Matsuoka, S. Nagamachi, K. Okada,
K. Maeda, and H. Shimizu, Nucl. Phys. A344, 41 (1980).
[sco90] W. Scobel, M. Trabandt, M. Blann, B. A. Pohl,
B. A. Remington, R. C. Byrd, C. C. Foster, R. Bonetti,
C. Chiesa, and S. M. Grimes, Phys. Rev. C41, 2010 (1990).
[tra89] M. Trabandt, W. Scobel, M. Blann, B.A. Pohl, R.C. Byrd,
C.C. Foster, R. Bonetti, and S.M. Grimes, Phys. Rev. C39,
452 (1989).
[wu79] J.R. Wu, C.C. Chang, and H.D. Holmgren, Phys. Rev. C19,
698 (1979).

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Last reviewed: 27 October 2010