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28-Ni- 64 LANL,ORNL EVAL-SEP97 S.CHIBA,M.B.CHADWICK,HETRICK
Ch97,Ch99 DIST-JAN09 20090105
----JEFF-311 MATERIAL 2843 REVISION 2
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
** **
** Original data taken from: JEFF-3.1 **
** **
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***************************** JEFF-3.1 *************************
** **
** Original data taken from: ENDF/B-VI.8 **
** **
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ENDF/B-VI MOD 4 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 Q-value for radiative capture was also updated in File 3.
Details of these changes are described in Los ALamos National
Laboratory report, LA-13812 (2001).
****************************************************************
ENDF/B-VI MOD 3 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.5 (Mod2) 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, Di97, Fa66, Du67].
The data for natural Ni were also used because there was not
enough data for Ni-64 at MeV region. The data for natural Ni were
transformed to the Ni-64 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 geometircal 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-64 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-64 was considered by the DWBA-mode calculation of ECIS95
[Ra96]:
Jpi Ex(MeV) Deformation length
2+ 1.3458 0.9215
3- 3.56 0.838
The data for 2+ level was retrieved from the literature [Ra87].
The deformation length for the 3- level was scaled from the same
quantity for Ni-62 according to A**(1/3) law.
****************************************************************
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, 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, report KFK-1000 (1968)
[Co67] J.L. Cook, H. Ferguson, and A.R. DeL Musgrove, Aust.J.
Phys. 20, 477 (1967)
[De89] J.P. Delaroche, Y. Wang and J. Rapaport, Phys.Rev.C 39,
391 (1989)
[Di97] F. Dietrich et al., private communication (1997).
[Du67] Yu.V. Dukarevich et al., Nucl.Phys. A92, 433 (1967)
[Fa66] J.A. Farrel et al, Ann.Phys. 36, 367 (1966)
[Fe80] M.B. Fedorov et al., 80Kiev, 1, 309(1980)
[Gi65] A. Gilbert and A.G.W. Cameron, 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, Z.Phys.A 283, 401 (1977)
[Ka85] C. Kalbach, Los Alamos National Laboratory report
LA-10248-MS (1985)
[Ka88] C. Kalbach, Phys.Rev.C 37, 2350 (1988); see also
C. Kalbach and F. M. Mann, Phys.Rev.C 23, 112 (1981)
[Ko90] J. Kopecky and M. Uhl, Phys.Rev.C 41, 1941 (1990)
[Ko97] A. Koning and J.P. Delaroche, private communication.
[La83] D.C. Larson et al, report 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, private communication (1973) [EXFOR 10342]
[Pe82] C.M. Perey et al, report ORNL-5893 (1982)
[Pe88] Pedroni et al, Phys.Rev.C 38, 2052 (1988)
[Po81] W. Poenitz, Nuclear Data Evaluation Methods and
Procedures, Proc. Conf., Upton, NY, 1981, Brookhaven report
BNL-NCS-51363 (1981) p. 249
[Ra87] S. Raman et al, At. Data Nucl. Data Tables, 36, 1(1987).
[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.C 7, 248 (1973)
[Sm79] A.B. Smith et al., Nucl.Sci.Eng., 72, 293 (1979)
[Sm91] D.L. Smith, "Probability, Statistics, and Data Uncertainty
in Nuclear Science and Technology" (American Nuclear Society,
1991)
[We96] H.P. Wellisch and D. Axen, Phys.Rev.C 54, 1329 (1996)
[Yo92] P.G. Young, E.D. Arthur, and M.B. Chadwick, Los Alamos
report LA-12343-MS (1992)
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ENDF/B-VI MOD 2 Revision, July 1991, (ORNL)
REVISION 1 CHANGES
The secondary particle distributions for MF=6, MT=51-52 were
corrected-to-center of mass, not laboratory coordinates.
The elastic transformation matrix was removed.
****************************************************************
ENDF/B-VI MOD 1 Evaluation, October 1989,
D.M. Hetrick, C.Y. Fu, N.M. 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 reference (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 EV TO 600 KEV THE SCATTERING
CROSS SECTION IS GIVEN COMPLETELY BY THE RESONANCE
PARAMETERS. FOR TOTAL AND CAPTURE, A CONTRIBUTION IS
ADDED FROM 40-600 KEV DUE TO THE CAPTURE CROSS SECTION
(SEE 3-102 BELOW). NO BACKGROUND FILES ARE GIVEN.
THERMAL CROSS SECTIONS ARE: TOTAL 1.53 B, ELASTIC SCATTER-
ING .0163, AND CAPTURE 1.52 B.
NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION
OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE
PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON
A FINER ENERGY GRID THAN GIVEN IN 4/2.
3-1 TOTAL CROSS SECTION: 1.E-5 EV TO 600 KEV GIVEN BY
RESONANCE PARAMETERS, AND A CONTRIBUTION FROM 40 TO 600
KEV SUPPLEMENTS THE RESONANCE CAPTURE. FROM 600 KEV TO
20 MEV, NAT NI DATA OF REF. (6) WERE USED AS NO 64NI
DATA AVAILABLE.
3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY
SUBTRACTING THE NONELASTIC FROM THE TOTAL
3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22,
3-28, 3-102, 3-103, 3-104, AND 3-107.
3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, AND
3-91.
3-16 (N,2N) CROSS SECTIONS WERE CALCULATED BY THE TNG
CODE (1,2,3,4). NO DATA AVAILABLE.
3-22 (N,NA)+(N,AN) CROSS SECTIONS WERE CALCULATED BY TNG. NO
DATA AVAILABLE OTHER THAN TOTAL ALPHA EMISSION CROSS
SECTION.
3-28 (N,NP)+(N,PN) CROSS SECTIONS WERE CALCULATED BY THE TNG
CODE (1,2,3,4). SPARSE DATA AVAILABLE DISAGREE. NOTE
THAT THE (N,D) CROSS SECTION WAS TAKEN FROM ENDF/B-V FOR
NAT NI (7) BUT NORMALIZED TO BE SMALLER BY A FACTOR OF 6.4
SO THAT THE (N,NP)+(N,PN)+(N,D) AGREES WITH THE DATA OF
QAIM (8). (SEE 3-104 BELOW).
3-51 TO 3-52 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE
FROM TNG (1,2,3,4).
3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM (TNG
CALCULATED).
3-102 (N,G) CAPTURE CROSS SECTION IS GIVEN COMPLETELY BY THE
RESONANCE PARAMETERS FROM 1.E-5 EV TO 40 KEV. WHILE THE
RESONANCE PARAMETERS CONTRIBUTE UP TO 600 KEV, AN
ADDITIONAL CONTRIBUTION FROM THE TNG CALCULATION IS
INCLUDED FROM 40 TO 600 KEV IN 3/102, DUE TO INCOMPLETE
EXPERIMENTAL CAPTURE RESONANCE INFORMATION. THE SAME
NORMALIZATION (0.4) USED FOR 58,60NI WAS ASSUMED FOR 64NI;
THE NORMALIZED TNG CALCULATIONS WERE USED FROM 600 KEV TO
20 MEV.
3-103 (N,P) CROSS SECTIONS WERE CALCULATED BY THE TNG
CODE (1,2,3,4).
3-104 (N,D) CROSS SECTIONS WERE TAKEN FROM ENDF/B-V FOR NAT. NI
BUT NORMALIZED TO BE SMALLER BY A FACTOR OF 6.4 SO THAT
THE (N,NP)+(N,PN)+(N,D) MATCHED THE DATA OF QAIM (8) AT
14.5 MEV.
3-107 (N,A) CROSS SECTIONS WERE CALCULATED BY THE
TNG CODE (1,2,3,4) BUT NORMALIZED TO BE LARGER BY A FACTOR
OF 12.5 SO THAT THE CROSS SECTIONS WOULD FIT THE DATA OF
QAIM ET AL. (9) AND KNEFF ET AL. (10).
4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR
ELASTIC SCATTERING ARE 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 63NI 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.
6-22 (N,NA)+(N,AN); INCLUDES SIMPLE CONSTANT YIELDS FOR THE
NEUTRON, ALPHA, AND 60FE 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.
6-28 (N,NP)+(N,PN); INCLUDES SIMPLE CONSTANT YIELDS FOR THE
NEUTRON, P, AND 63CO 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 6-52 INELASTIC SCATTERING EXCITING LEVELS;
ASSUMED ISOTROPIC.
6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES
SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 64NI
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 64CO 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 61FE 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 12-52 BRANCHING RATIOS FOR THE LEVELS ARE GIVEN.
12-102 (N,G) CAPTURE; MULTIPLICITIES FOR ENERGIES LESS THAN
1.0 MEV WERE TAKEN FROM ENDF/B-V, BUT ADJUSTED FOR ENERGY
BALANCE; TNG CALCULATIONS WERE USED FOR EN = 2 AND 5 MEV.
14-51 THROUGH 14-52 AND 14-102 GAMMA RAY ANGULAR DISTRIBUTIONS
ASSUMED TO BE ISOTROPIC.
15-102 (N,G) CAPTURE; AS IN 12-102.
----------------------------------------------------------------
UNCERTAINTY FILES
AN LB=8 SECTION IS INCLUDED FOR ALL NON-DERIVED FILES AS
REQUIRED BY ENDF/B-VI.
33-1 UNCERTAINTIES ARE DERIVED FROM 1.E-5 TO 10 EV. FROM 10
EV TO 20 MEV THEY ARE EXPLICIT, USING LB=0,1 AND 8.
33-2 FROM 1.E-5 TO 10 EV, UNCERTAINTIES ARE EXPLICIT, BASED
UPON THERMAL UNCERTAINTY AND OTHER DATA. FROM 10 EV TO
20 MEV THE FILES ARE DERIVED.
33-3 FROM 1.E-5 TO 600 KEV UNCERTAINTIES ARE DERIVED. FROM 600
KEV TO 20 MEV UNCERTAINTIES ARE EXPLICIT, USING LB=1 AND 8
33-4 UNCERTAINTIES ARE ALL DERIVED.
33-16 UNCERTAINTIES FOR (N,2N) ARE EXPLICIT, ESTIMATED FROM TNG
33-22 UNCERTAINTIES FOR (N,NA) ARE EXPLICIT, ESTIMATED FROM TNG
33-28 UNCERTAINTIES FOR (N,NP) ARE EXPLICIT, ESTIMATED FROM TNG
33-51-91 UNCERTAINTIES FOR INELASTIC SCATTERING ARE EXPLICIT,
BASED ON DATA AND CALCULATION UNCERTAINTIES.
33-102 UNCERTAINTIES ARE EXPLICIT, BASED ON THERMAL DATA AT LOW
ENERGIES, AND CALCULATED RESULTS ABOVE 600 KEV.
33-103 UNCERTAINTIES ESTIMATED FROM TNG.
33-104 UNCERTAINTIES ESTIMATED, BASED ON DATA.
33-107 UNCERTAINTIES ESTIMATED FROM TNG.
****************************************************************
REFERENCES:
(1) C.Y. Fu, Oak Ridge report ORNL/TM-7042 (1980)
(2) C.Y Fu, Neutron Cross Sections from 10 to 50 MeV, Upton, NY,
May 1980, Brookhaven report BNL-NCS-51425 () p. 675
(3) K. Shibata and C.Y. Fu, Oak Ridge report ORNL/TM-10093 (1986)
(4) D.M. Hetrick, C.Y. Fu and D.C. Larson, Oak Ridge report
ORNL/TM-10219 [ENDF-344] (1987)
(5) S.F. Mughabghab, M. Divadeenam and N.E. Holden, "Neutron
Cross Sections, Vol. 1, Part A (Academic Press, 1981)
(6) D.C. Larson, N.M. Larson, J.A. Harvey, et al., Oak Ridge
report ORNL/TM8203 [ENDF-333] (1983)
(7) M. Divadeenam, Brookhaven report BNL-NCS-51346 [ENDF-294]
(1979)
(8) S.M. Qaim, Nucl.Phys., A382, 255 (1982)
(9) S.M. Qaim, R. Wolfle, M.M. Rahman and H. Ollig, Nucl.Sci.
Eng., 88, 143 (1984)
(10) D.W. Kneff, B.M. Oliver, H. Farrar IV and L.R. Greenwood,
Nucl.Sci.Eng., 92, 491 (1986)
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