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2.806100+4 6.040800+1 1 0 2 5
0.000000+0 0.000000+0 0 0 0 6
1.000000+0 1.500000+8 8 0 10 31
0.000000+0 0.000000+0 0 0 418 1
28-Ni- 61 LANL,ORNL EVAL-SEP97 S.CHIBA,M.B.CHADWICK,HETRICK
Ch97,Ch99 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 2834 REVISION 3
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: ENDF/B-VI.8 **
** **
******************************************************************
******************************************************************
ENDF/B-VI MOD 5 Revision, June 2000, S.C. Frankle, R.C. Reedy,
P.G. Young (LANL)
The secondary gamma-ray spectrum for radiative capture (MF 12,
MT 102) has been updated for new experimental data at incident
neutron energies up to 1 keV. The previous pure continuum repre-
sentation at thermal energies is replaced by 77 discrete gamma
rays, plus a continuum from a calculation with the GNASH code.
The MF=12, MT=102 yields above 1 keV were adjusted slightly to
force energy conservation.
The Q-value for radiative capture was also updated in File 3.
Details of these changes are described in Frankel et al. [Fr01].
****************************************************************
ENDF/B-VI MOD 4 Evaluation, September 1997, S. Chiba,
M.B. Chadwick, P.G. Young (LANL), and
A.J. Koning (ECN)
Los Alamos LA150 Library, produced with FKK/GNASH/GSCAN code
in cooperation with ECN Petten.
This evaluation provides a complete representation of the
nuclear data needed for transport, damage, heating,
radioactivity, and shielding applications over the incident
neutron energy range from 1.0E-11 to 150 MeV. The discussion
here is divided into the region below and above 20 MeV.
INCIDENT NEUTRON ENERGIES < 20 MeV
Below 20 MeV the evaluation is based completely on the ENDF/B-
VI (Mod3) evaluation by Larson, C. Perey, Hetrich, and
Fu.
INCIDENT NEUTRON ENERGIES > 20 MeV
The ENDF/B-VI Release 2 evaluation extends to 20 MeV and
includes cross sections and energy-angle data for all
significant reactions. The present evaluation utilizes a more
compact composite reaction spectrum representation above 20 MeV
in order to reduce the length of the file. No essential data for
applications is lost with this representation.
The evaluation above 20 MeV utilizes MF=6, MT=5 to represent
all reaction data. Production cross sections and emission
spectra are given for neutrons, protons, deuterons, tritons,
alpha particles, gamma rays, and all residual nuclides produced
(A>5) in the reaction chains. To summarize, the ENDF sections
with non-zero data above En = 20 MeV are:
MF=3 MT= 1 Total Cross Section
MT= 2 Elastic Scattering Cross Section
MT= 3 Nonelastic Cross Section
MT= 5 Sum of Binary (n,n') and (n,x) Reactions
MF=4 MT= 2 Elastic Angular Distributions
MF=6 MT= 5 Production Cross Sections and Energy-Angle
Distributions for Emission Neutrons, Protons,
Deuterons, Tritons, and Alphas; and Angle-
Integrated Spectra for Gamma Rays and Residual
Nuclei That Are Stable Against Particle Emission
The evaluation is based on nuclear model calculations that
have been benchmarked to experimental data, especially for n +
Ni58 and p + Ni58 reactions (Ch97). We use the GNASH code system
(Yo92), which utilizes Hauser-Feshbach statistical,
preequilibrium and direct-reaction theories. Spherical optical
model calculations are used to obtain particle transmission
coefficients for the Hauser-Feshbach calculations, as well as
for the elastic neutron angular distributions.
Cross sections and spectra for producing individual residual
nuclei are included for reactions. The energy-angle-correlations
for all outgoing particles are based on Kalbach systematics
(Ka88).
A model was developed to calculate the energy distributions of
all recoil nuclei in the GNASH calculations (Ch96). The recoil
energy distributions are represented in the laboratory system in
MT=5, MF=6, and are given as isotropic in the lab system. All
other data in MT=5,MF=6 are given in the center-of-mass system.
This method of representation utilizes the LCT=3 option approved
at the November, 1996, CSEWG meeting.
Preequilibrium corrections were performed in the course of the
GNASH calculations using the exciton model of Kalbach (Ka77,
Ka85), validated by comparison with calculations using Feshbach,
Kerman, Koonin (FKK) theory [Ch93]. Discrete level data from
nuclear data sheets were matched to continuum level densities
using the formulation of Gilbert and Cameron (Gi65) and pairing
and shell parameters from the Cook (Co67) analysis. Neutron and
charged- particle transmission coefficients were obtained from
the optical potentials, as discussed below. Gamma-ray
transmission coefficients were calculated using the Kopecky-Uhl
model (Ko90).
SOME Ni-SPECIFIC INFORMATION CONCERNING THE EVAL.
The neutron total cross section was evaluated based on the
least-squares method with GMA code system (Po81) taking account of
the experimental data(Ci68, Pe73, Sc73, La83, Sm92, Di97). The
data for natural Ni and Ni-58 were used because there was no data
for Ni-61. These data were transformed to the Ni-61 cross section
according to A*(2/3) law. In the GMA analysis, the systematic
error was assumed to be 1 % for all the data set. Result of the
GMA evaluation was used as the evaluated total cross section data
above 20 MeV.
The evaluated total cross section data (1 to 250 MeV) and s-wave
strength function (Mu81) were used to obtain the neutron optical
potential parameters. The parameter estimation was carried out
based on Marquart-Bayesian approach (Sm91), where ECIS95 code was
used for the optical model calculation. We have employed the
energy dependence of the optical potential similar to Delaroche's
work(De89). The initial potential parameters were adopted from
Koning and Delaroche (Ko97). Total of 7 parameters concerning the
central potential depth were estimated with associated covariance
matrix, while the geometrical parameters were fixed to the result
of a similar search for n + Ni-58. Presently obtained potential
was used for the calculation of neutron transmission coefficients
and DWBA cross sections in the energy region above 20 MeV. Below
20 MeV, the Harper neutron potential (Ha82) was used for the
calculation of transmission coefficients.
The proton optical potential was also searched for to obtain a
good description of proton-total reaction cross section as
predicted by Wellisch-Axen systematic (We96) above 50 MeV. The
parameter estimation was carried out by the Marquart-Bayesian
approach similar to the neutron OMP, but trying to seek the best
parameter to reproduce the reaction cross sections compiled by
Carlson (Ca96) and Wellisch values. The experimental data in
Carlson (Ca96) was scaled for Ni-61 according to A**(2/3) law. In
this search, the geometrical parameters were fixed to be same as
the neutron potential. The present potential gives a good
description of the proton total reaction cross section from 10 MeV
to 250 MeV. However, after some trial and error to reproduce both
the elastic scattering and reaction cross section data for Ni-58,
we have employed the following combination of proton potentials:
0 to 5 MeV : Harper potential (Ha82)
6 to 47 MeV : Koning and Delaroche (Ko97)
48 to 260 MeV : Present OMP
For deuterons, the Lohr-Haeberli (Lo74) global potential was used;
for alpha particles the McFadden-Satchler (Mc66) potential was
used; and for tritons the Becchetti-Greenlees (Be71) potential was
used. The He-3 channel was ignored.
The direct collective inelastic scattering to the following levels
in Ni-61 was considered by the DWBA-mode calculation of ECIS95:
Jpi Ex(MeV) Deformation length
1/2- 0.2830 0.31703
5/2- 0.9086 0.54912
7/2- 1.0152 0.63407
3/2- 1.0996 0.44835
The deformation lengths were estimated assuming a weak-coupling of
3/2- neutron hole to the excited 2+ core in Ni-62.
****************************************************************
REFERENCES
[Be71] F.D. Becchetti, Jr., and G.W. Greenlees in
"Polarization Phenomena in Nuclear Reactions," (Ed: H.H.
Barschall and W. Haeberli, The University of Wisconsin Press,
1971) p.682.
[Bo71] P. Boschung et al, Nucl. Phys. A161, 593 (1971)
[Ca96] R. F. Carlson, Atomic Data and Nuclear Data Tables, 63,
93(1996).
[Ch93] M. B. Chadwick and P. G. Young, "Feshbach-Kerman-Koonin
Analysis of 93Nb Reactions: P --> Q Transitions and Reduced
Importance of Multistep Compound Emission," Phys. Rev. C 47,
2255 (1993).
[Ch96] M. B. Chadwick, P. G. Young, R. E. MacFarlane, and A.
J. Koning, "High-Energy Nuclear Data Libraries for Accelerator-
Driven Technologies: Calculational Method for Heavy Recoils,"
Proc. of 2nd Int. Conf. on Accelerator Driven Transmutation
Technology and Applications, Kalmar, Sweden, 3-7 June 1996.
[Ch97] M. B. Chadwick and P. G. Young, "Model Calculations of
n,p + 58,60,61,62,64Ni" in APT PROGRESS REPORT: 1 August - 1
September 1997, internal Los Alamos National Laboratory memo T-
2-97/MS-51, 8 September 1997 from R.E. MacFarlane to L. Waters.
[Ch99] M.B. Chadwick, P G. Young, G. M. Hale, et al., Los Alamos
National Laboratory report, LA-UR-99-1222 (1999)
[Ci68] S. Cierjack et al, KFK-1000(1968).
[Co67] J. L. Cook, H. Ferguson, and A. R. Musgrove, "Nuclear
Level Densities in Intermediate and Heavy Nuclei," Aust.J.Phys.
20, 477 (1967).
[De89] J.P. Delaroche, Y. Wang and J. Rapaport, Phys. Rev. C39,
391(1989).
[Di97] F. Dietrich et al., private communication (1997).
[Du67] Ju.V. Dukarevich et al., Nucl. Phys. A92, 433(1967)
[Fe80] M.B. Fedorov et al., 80Kiev, 1, 309(1980)
[Fr01] S.C. Frankle, R.C. Reedy, and P.G. Young, Los ALamos
National Laboratory Report, LA-13812 (2001).
[Gi65] A. Gilbert and A. G. W. Cameron, "A Composite Nuclear-
Level Density Formula with Shell Corrections," Can. J. Phys.
43, 1446 (1965).
[Gu85] P.P. Guss et al, Nucl. Phys. A438, 187(1985).
[Ha82] R.C. Harper and W.L. Alford, J. Phys. G. 8, 153(1982).
[Ka77] C. Kalbach, "The Griffin Model, Complex Particles and
Direct Nuclear Reactions," Z.Phys.A 283, 401 (1977).
[Ka85] C. Kalbach, "PRECO-D2: Program for Calculating
Preequilibrium and Direct Reaction Double Differential Cross
Sections," Los Alamos National Laboratory report LA-10248-MS
(1985).
[Ka88] C. Kalbach, "Systematics of Continuum Angular
Distributions: Extensions to Higher Energies," Phys.Rev.C 37,
2350 (1988); see also C. Kalbach and F. M. Mann, "Phenomenology
of Continuum Angular Distributions. I. Systematics and
Parameterization," Phys.Rev.C 23, 112 (1981).
[Ko90] J. Kopecky and M. Uhl, "Test of Gamma-Ray Strength
Functions in Nuclear Reaction Model Calculations," Phys.Rev.C
42, 1941 (1990).
[Ko97] A. Koning and J.P. Delaroche, private communication.
[La83] D.C. Larson et al, ORNL-TM-8203(1983).
[Lo74] J.M.Lohr and W.Haeberli, Nucl.Phys. A232,381(1974)
[Mc66] L. McFadden and G. R. Satchler, Nucl. Phys. 84, 177
(1966).
[Mu81] S.F. Mughabghab, M. Divadeenam and N.E. Holden, "Neutron
Cross Sections", Vol. 1, Part A, Academic Press (1981).
[Pe73] F.G. Perey, EXFOR 10342002 (1973).
[Pe82] C.M. Perey et al, ORNL-5893 (1982)
[Pe88] Pedroni et al, Phys. Rev. C38, 2052(1988).
[Po81] W. Poenitz, Proc. Conf. on Nuclear Data Evaluation Methods
and Procedures, Brookhaven National Laboratory Report BNL-NCS-
51363, p.249(1981).
[Ra96] J. Raynal, "Notes on ECIS94", Service de Physique
Theorique, Saclay, France (personal communication through A. J.
Koning, 1996).
[Sc73] W. Schimmerling et al., Phys. Rev. C7, 248(1973).
[Sm79] A.B. Smith et al., NSE, 72, 293 (1979)
[Sm91] D.L. Smith, "Probability, Statistics, and Data Uncertainty
in Nuclear Science and Technology", American Nuclear Society
(1991).
[Sm92] A.B. Smith et al., J. Phys. G. 18, 629(1992)
[We96] H.P. Wellisch and D. Axen, Phys. Rev. C54, 1329(1996).
[Ya79] Y. Yamanouti et al, EXFOR 10953002 (79Knox).
[Yo92] P. G. Young, E. D. Arthur, and M. B. Chadwick,
"Comprehensive Nuclear Model Calculations: Introduction to the
Theory and Use of the GNASH Code," LA-12343-MS (1992).
****************************************************************
ENDF/B-VI MOD 3 Revision, October 1997, V.McLane (NNDC)
MF=2 RESONANCE PARAMETERS
MT=151 Energy-dependent scattering radius added.
****************************************************************
ENDF/B-VI MOD 2 Revision, July 1991, (ORNL)
CHANGES
File 6: Seecondary particle distributions for MT=51-58 were
corrected-to-center of mass from laboratory coordinates.
The elastic transformation matrix was removed.
****************************************************************
ENDF/B-VI MOD 1 Evaluation, October 1989, D.M.Hetrick, C. Fu,
D. Larson (ORNL)
This work employed the Hauser-Feshbach code TNG [1,2,3].
The TNG code provides energy and angular distributions of
particles emitted in the compound and pre-compound reactions,
ensures consistency among all reactions, and maintains energy
balance. Details pertinent to the contents of this evaluation
can be found in Hetrick et al. [4].
DESCRIPTION OF FILES
(MF-MT)
1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS.
2-151 RESONANCE PARAMETERS; Taken from the compilation of
Mughabghab [5)]. From 1.E-5 to 70 keV the total, scattering
and capture cross sections are given completely by the
resonance parameters; no background files are given. The
thermal cross sections are given by the resonance
parameters:
Total 10.4 b, Elastic scattering 7.9 b, Capture 2.5 b.
Note that the flag has been set to allow the user to
calculate the angular distributions from the R-M resonance
parameters, if the user wants angular distributions on a
finer energy grid than given in File 4, MT=2.
3-1 TOTAL CROSS SECTION - 1.E-5 eV to 70 keV, given by the
resonance parameters. From 70 keV to 20 MeV, Natural Ni
data of Larson [6] were used as no 61Ni data were available.
3-2 ELASTIC SCATTERING CROSS SECTIONS: Obtained by
subtracting the nonelastic from the total.
3-3 NONELASTIC CROSS SECTION; Sum of 3-4, 3-16, 3-28, 3-102,
3-103, and 3-107.
3-4 TOTAL INELASTIC CROSS SECTION; Sum of 3-51, 3-52 to 3-58
and 3-91.
3-16 (N,2N) CROSS SECTIONS; Calculated by the TNG code
[1,2,3,4]. No data available.
3-28 (N,NP)+(N,PN) CROSS SECTIONS: Calculated by the TNG code
[1,2,3,4]. No data available.
3-51 to 3-58 INELASTIC SCATTERING EXCITING LEVELS; Results are
from TNG [1,2,3,4].
3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM: TNG
calculated but adjusted to include the cross section
subtracted from the (n,p) (see below) so that the (n,p)
agrees with measured data. This is reasonable because the
TNG calculations did not include a direct interaction
component and the nonelastic stays the same.
3-102 (N,G) CAPTURE CROSS SECTION: Given by resonance parameters
from 1.E-5 eV to 70 keV. Pointwise cross sections were
generated from the resonance parameters and binned. The
capture cross section from TNG was normalized to binned
data from 10-70 keV and used from 70 keV to 20 MeV.
3-103 (N,P) CROSS SECTIONS: Calculated by the TNG code
[1,2,3,4] but then adjusted to fit the data of Qaim et al.
[7]. The difference between the TNG results for (n,p) and
the data were added to the TNG results for 3-91 (see above).
3-107 (N,A) CROSS SECTIONS: Calculated by the TNG code
[1,2,3,4]. No data available.
3-111 (N,2P) CROSS SECTIONS: Calculated by the TNG code
[1,2,3,4]. No data available.
4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS FOR ELASTIC
SCATTERING: From ENDF/B-V.
If desired, angular distributions can be calculated by
the user on a finer energy grid from the R-M resonance
parameters in 2-151.
6-16 (N,2N) REACTION; Includes simple constant yields for the
neutron and 60Ni residual, and energy dependent yield based
on TNG calculated gamma-ray spectra for the gamma ray; TNG
calculated normalized distributions are given for each
product. Isotropy is assumed.
6-28 (N,NP)+(N,PN); Includes simple constant yields for the
neutron, p, and 60Co residual, and energy dependent yield
based on TNG calculated gamma-ray spectra for the gamma ray;
calculated normalized distributions are given for each
product. Isotropy is assumed.
6-51 through 6-58 INELASTIC SCATTERING EXCITING LEVELS;
Assumed isotropic.
6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; Includes
simple constant yields for the neutron and 61Ni residual,
and energy dependent yield based on TNG calculated gamma-
ray spectra for the gamma ray; TNG calculated normalized
distributions are given for each. Isotropy is assumed.
6-103 (N,P) REACTION; Includes simple constant yields for p
and 61Co residual, and energy dependent yield based on
calculated gamma-ray spectra for gamma ray; calculated
normalized distributions are given for each product.
Isotropy is assumed.
6-107 (N,A) REACTION; Includes simple constant yields for a
and 58Fe residual, and energy dependent yield based on
calculated gamma-ray spectra for gamma ray; calculated
normalized distributions are given for each product.
Isotropy is assumed.
12-51 through 12-58 BRANCHING RATIOS FOR THE LEVELS are given.
12-102 (N,G) CAPTURE; Multiplicities for energies less than
1.0 MeV taken from ENDF/B-V for natural Ni but adjusted for
energy balance; TNG calculations were used for energies
2.0 and 5.0 MeV.
14-51 through 14-58 and 14-102 GAMMA RAY ANGULAR DISTRIBUTIONS;
Assumed to be isotropic.
15-102 (N,G) CAPTURE; As in 12-102.
UNCERTAINTY FILES: All non-derived uncertainty files contain an
LB=8 component as required by ENDF/B-VI.
33-1 Uncertanties are derived from 1.E-5 to 100 eV. From 100
eV to 20 MeV the uncertainties are explicit, using LB=0,1
and 8.
33-2 Explicit from 1.E-5 to 100 eV, using LB=1 and 8. From
100 eV to 20 MeV the uncertainties are derived.
33-3 Derived from 1.E-5 to 70 keV; explicit from 70 keV to 20
MeV using LB=1 and 8.
33-4 Uncertainties all derived.
33-16 Uncertainties explicit, estimated from TNG.
33-28 Uncertainties explicit, estimated from TNG.
33-51 through 33-91 Uncertainties explicit, estimated from data
and TNG.
33-102 Uncertainties based on thermal capture at low energies,
data to 70 keV, and TNG calculations to 20 MeV.
33-103 Based on data and TNG calculations.
33-107 Based on TNG calculations.
33-111 Based on TNG calculations.
****************************************************************
REFERENCES
(1) C.Y. Fu, Oak Ridge National Laboratory report ORNL/TM-7042
(1980)
(2) C.Y Fu, Neutron Cross Sections from 10 to 50 MeV, Proc.
Symp. Upton, NY, May 12-14, 1980, Brookhaven National
Laboratory report BNL-NCS-51425 (1980) p.675
(3) K. Shibata and C.Y. Fu, Oak Ridge National Laboratory report
ORNL/TM-10093 (1986)
(4) D.M. Hetrick, C.Y. Fu, and D.C. Larson, Oak Ridge National
Laboratory report ORNL/TM-10219 [ENDF-344] (1987)
(5) S.F. Mughabghab, M. Divadeenam, and N.E. Holden, Neutron
Cross Sections, Vol. 1, Neutron Resonance Parameters and
Thermal Cross Sections, Part A, Z=1-60, (Academic Press,
1981)
(6) D.C. Larson, N.M. Larson, J.A.Harvey, N.W. Hill and C.H.
Johnson, Oak Ridge National Laboratory report ORNL/TM8203
[ENDF-333] (1983)
(7) S.M. Qaim, R. Wolfle, M.M. Rahman, and H. Ollig, Nucl.Sci.
Eng., 88, 143 (1984) and N.I. Molla and S.M. Qaim, Nucl.Phys.
A283, 269 (1977)
************************ C O N T E N T S ***********************
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