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29-Cu- 63 LANL,ORNL EVAL-FEB98 A.KONING,M.CHADWICK,HETRICK
Ch98,Ch99 DIST-JAN09 20090105
----JEFF-311 MATERIAL 2925 REVISION 3
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
** **
** Original data taken from: JEFF-3.1 **
** **
******************************************************************
***************************** JEFF-3.1 *************************
** **
** Original data taken from: ENDF/B-VI.8 **
** **
******************************************************************
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ENDF/B-VI MOD 5 Revision, May 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 Frankel et al. [Fr01].
****************************************************************
ENDF/B-VI MOD 4 Evaluation, February 1998, A.J. Koning (ECN),
M.B. Chadwick, P.G. Young (LANL)
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 (Mod 3) evaluation by D. Hetrick, C.Y. Fu, and D. Larson.
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 +
Cu65 and p + Cu65 reactions [Ch98]. We use the GNASH code system
[Yo92], which utilizes Hauser-Feshbach statistical, preequilib-
rium 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 [Ch96a]. 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 Ignatyuk et al. [Ig75] 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].
SPECIFIC INFORMATION CONCERNING THE 63Cu EVALUATION
This evaluation is documented in some detail in Ref. [Ko98b].
The neutron total cross section above 20 MeV was obtained by
evaluating experimental data, with a particular emphasis on the
Finlay [Fi93] elemental data. This resulted in an evaluated
elemental Cu total cross section; to obtain an isotopic 63Cu total
cross section, it was assumed that 63Cu and 65Cu have total cross
sections in an A**2/3 ratio to one another. The total neutron
nonelastic cross section was obtained directly from an optical
model calculation (see below), after verifying that it was in good
agreement with the experimental data [Ko98b].
To obtain the neutron optical potential we used total cross
section data from 1.2 to 4.5 MeV [Gu86] and from 5.3 to 600 MeV
[Fi93], and elastic scattering angular distribution data from 1.6
to 96 MeV [Br50, Sa60, Ki74, El82, Gu86]. The optical potential
parameters were obtained using a combination of a grid search code
and the interactive optical model viewer ECISVIEW [Ko97], both
built around the coupled channels code ECIS96 [Ra94]. The energy
dependence of the optical model parameters is as described in
[Ko98]. This optical potential was used for the calculation, with
ECIS96, of neutron transmission coefficients and DWBA cross
sections for the entire energy region above 20 MeV.
Due to the lack of proton elastic scattering data in numerical
form, we used a combination of global optical models for the
proton channel. The Becchetti-Greenlees potential [Be69]was
adopted below 47 MeV, and the non-relativistic version of the
Madland potential [Ma88] above 47 MeV. At this particular energy
point the two potentials join smoothly.
For deuterons, the Lohr-Haeberli global potential [Lo74] was used;
for alpha particles the Moyen potential (MacFadden-Satchler
[Ma66]) was used; and for tritons the Becchetti-Greenlees
potential [Be71] was used. The He-3 channel was ignored, due to
its small importance.
Following Delaroche et al. [De82], we adopted the weak-coupling
model for direct collective inelastic scattering for Cu-63, using
Ni-64 as a basis. For the calculation of the cross sections,
ECIS96 was used in DWBA mode. We used the following direct
transitions for Cu-63 (ground state 3/2- ) :
Jpi Ex(MeV) Deformation lengths
0.5- 0.669 Delta(2)=0.319
2.5- 0.962 Delta(2)=0.552
3.5- 1.327 Delta(2)=0.638
1.5- 1.547 Delta(2)=0.451
1.5- 3.382 Delta(3)=0.313
2.5- 3.632 Delta(3)=0.384
3.5- 3.882 Delta(3)=0.444
4.5- 4.132 Delta(3)=0.496
No measurements exist for neutron-induced emission spectra above
20 MeV for 63Cu. However, for Cu-65 there exists 25.7 MeV (n,xn)
data by Marcinkowski et al [Ma83]. This has been used to benchmark
the Cu-65 data. Without adjusting any of the level density or pre-
equilibrium parameters the GNASH calculation was in good agreement
with these data. Hence we also adopted these parameters for the
whole energy region for Cu-63.
****************************************************************
REFERENCES
[Ab93] W. Abfalterer, R.W. Finlay, S.M. Grimes, and V. Mishra,
Phys.Rev. C47, 1033 (1993)
[Al83] R. Alarcon and J. Rapaport, Nucl.Phys. A458, 502 (1986)
[Ar80] E.D. Arthur and P.G. Young, 'Evaluation of Neutron Cross
Sections to 40 MeV for 54,56Fe," Proc. Sym. on Neutron Cross
Sections from 10 to 50 MeV, 12-14 May 1980, Brookhaven National
Laboratory [Eds. M. R. Bhat and S. Pearlstein, BNL-NCS- 51245,
1980] p. 731.
[Be69] F.D. Becchetti, Jr., and G.W. Greenlees, Phys.Rev. 182,
1190 (1969)
[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.
[Be92] O. Bersillon, "SCAT2 - A Spherical Optical Model Code,"
in Proc. ICTP Workshop on Computation and Analysis of Nuclear
data Relevant to Nuclear Energy and Safety, February-March,
1999 Trieste, Italy, to be published in World Scientific Press,
and Progress Report of the Nuclear Physics Division, Bruyeres-
le-Chatel 1977, CEA-N-2037 (1978) p.111
[Br50] S. Bratenahl, S. Fernbach, R.H. Hildebrand et al.,
Phys.Rev. 77, 597 (1950)
[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
[Ch98] M. B. Chadwick and P. G. Young, "GNASH Calculations of
n,p + Cu isotopes and Benchmarking of Results" in APT PROGRESS
REPORT: 1 February - 1 March 1998, internal Los Alamos National
Laboratory memo, 6 Mar.1998 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)
[Co67] J.L. Cook, H. Ferguson, and A.R. DeL Musgrove, Aust.J.
Phys. 20, 477 (1967)
[De82] J.P. Delaroche, S.M. El-Kadi, P.P. Guss, C.E. Floyd and
R.L. Walter, Nucl. Phys. A390, 541 (1982).
[El82] S.M. El-Kadi, C.E. Nelson, F.O. Purser et al., Nucl.Phys.
A390, 509 (1982)
[Fi93] R. W. Finlay, W. P. Abfalterer, G. Fink et al., Phys.Rev.
C 47, 237 (1993)
[Fr01] S.C. Frankle, R.C. Reedy, and P.G. Young, Los ALamos
National Laboratory Report, LA-13812 (2001).
[Gu86] P. Guenther, D.L. Smith, A.B. Smith, J.F. Whalen, Nucl.
Phys. A448, 280 (1986)
[Ig75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov.J.
Nucl.Phys. 21, 255 (1975); translation of Yad.Fiz. 21, 485
(1975)
[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)
[Ki74] W.E. Kinney, F.G. Perey, Oak Ridge report ORNL-4908 (1974)
[Ko90] J. Kopecky and M. Uhl, Phys.Rev.C 41, 1941 (1990)
[Ko97] A.J. Koning, J.J. van Wijk and J.-P. Delaroche, "ECISVIEW:
A Graphical Interface for ECIS95", Proceedings of the NEA
Specialists' Meeting on the Nucleon Nucleus Optical Model up to
200 MeV, Bruyeres-le-Chatel, November 13-15 1996. Available at
http://db.nea.fr/html/science/om200/.
[Ko98] A.J. Koning, J.-P. Delaroche and O. Bersillon, "Nuclear
Data for Accelerator-Driven Systems: Nuclear models, Experiment
and Data Libraries", to appear in Mucl. Instr. Meth. A (1998).
[Ko98b] A.J. Koning, M.B. Chadwick, and P.G. Young, "ENDF/B-VI
neutron and proton datafiles up to 150 MeV for 63Cu and 65Cu",
Los Alamos National Laboratory report LAUR- (1998); ECN lab and
JEFF report (1998).
[Lo74] J.M. Lohr and W. Haeberli, Nucl.Phys. A232, 381 (1974)
[Ma66] Macfadden and Satchler, Nuc.Phys. 84, 177 (1966)
[Ma83] A. Marcinkowski, R.W. Finlay, G. Randers-Pehrson et al.,
Nucl.Phys. A402, 220 (1983)
[Ma88] D.G. Madland, "Recent Results in the Development of a
Global Medium-Energy Nucleon-Nucleus Optical-Model Potential,
"Proc. OECD/NEANDC Specialist's Mtg. on Preequilibrium Nuclear
Reactions, Semmering, Austria, 10-12 Feb. 1988, NEANDC-245 'U'
(1988).
[Pe63] C.M. Perey and F.G. Perey, Phys.Rev. 132, 755 (1963)
[Ra94] J. Raynal, Notes on ECIS94, CEA Saclay Report CEA-N-2772
(1994)
[Sa60] G.L. Salmon, Nucl.Phys. 21, 15 (1960)
[Yo92] P.G. Young, E.D. Arthur, and M.B. Chadwick, report
LA-12343-MS (1992)
****************************************************************
ENDF/B-VI MOD 3 Revision, July 1991 (ORNL)
MOD 3 changes
1) Corrections to MF=6, MT=65 at 17.0 MeV to prevent negative
values in the angular distribution.
2) Corrections to MF=33, MT=102
****************************************************************
* Note there was no MOD 2 released.
****************************************************************
ENDF/B-VI MOD 1 Evaluation, October 1989, D. Hetrick, F.Y. Fu,
D. Larson (ORNL)
This work employed several nuclear model codes including the
optical-model code GENOA [1], the Distorted Wave Born
Approximation (DWBA) program DWUCK [2], and the Hauser-Feshbach
code TNG [3,4]. 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 and extensive comparisons of calculations with
experimental data can be found in reference [5].
----- DESCRIPTION OF FILES
(MF-MT)
1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS.
2-151 RESONANCE PARAMETERS WERE TAKEN FROM MUGHABGHAB[6]. POINT
WISE RECONSTRUCTION COMPARED WITH DATA [7] SHOWED POORER
FIT ABOVE 100 KEV, SO THE RESONANCE REGION WAS CUT OFF AT
99.5 KEV. REICH-MOORE PARAMETERS ARE GIVEN. AGREEMENT
WITH DATA COULD BE IMPROVED WITH ADDITION OF A BACKGROUND
FILE IN 3/1, BUT THIS IN GENERAL GIVES TOO LARGE AN
AVERAGE CROSS SECTION, WHEN BINNED IN 10 KEV BINS AND
COMPARED WITH THE BINNED DATA. THIS IS PROBABLY DUE TO
TOO LARGE AN ESTIMATE OF NEUTRON WIDTHS FOR RESONANCES
SEEN ONLY IN CAPTURE AND NOT IN TRANSMISSION.
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 THE TOTAL CROSS SECTION IS GIVEN BY RESONANCE PARAMETERS
FROM 1.E-5 EV TO 99.5 KEV. FROM 1.E-5 TO 1 EV, -0.9B IS
GIVEN TO REDUCE THE ELASTIC AND GIVE THE CORRECT TOTAL
THERMAL CROSS SECTION (9.6 B). FROM 1 EV TO 170 EV THIS
GOES LINEARLY TO ZERO. A SMALL CONTRIBUTION FROM 3/102 IS
REQUIRED FROM 60 TO 99.5 KEV, WHICH WHEN ADDED TO 2/151
REPRODUCES THE CAPTURE DATA. FROM 99.5 KEV TO 1.12 MEV
CU63 DATA FROM [7] IS USED, AFTER APPROPRIATE AVERAGING.
ABOVE THIS, NO ISOTOPIC DATA IS AVAILABLE. FROM 1.12 TO
4.0 MEV,NAT CU DATA OF PEREY [8] USED IN V5 IS RETAINED.
FROM 4.0 TO 20 MEV, NAT CU DATA OF LARSON ET.AL [9] IS
AVERAGED AND USED. COMPARISONS FROM 1.2 TO 4.5
MEV WITH AVERAGED ARGONNE DATA FOR NAT CU [10] SHOW
1% AGREEMENT.
3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY
SUBTRACTING THE NONELASTIC (3-3) FROM THE TOTAL. THE
THERMAL VALUE OF 5.1 B IS REPRODUCED.
3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22,
3-28, 3-102, 3-103, 3-104, 3-106, AND 3-107.
3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, ..
.., 3-72, AND 3-91
3-16 (N,2N) CROSS SECTIONS WERE TAKEN FROM THE GLUCS [11]
CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL-
TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS
SECTIONS [12].
3-22 (N,NA) CROSS SECTIONS WERE CALCULATED BY THE TNG
CODE [3,4,5]. NO DATA AVAILABLE OTHER THAN A-EMISSION.
3-28 (N,NP) CROSS SECTIONS WERE CALCULATED BY THE TNG
CODE [3,4,5]. DATA SCARCE FOR THIS REACTION (SEE (5)).
3-51 TO 3-72 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE
FROM TNG [3,4,5] WHICH INCLUDES DIRECT INTERACTION
CROSS SECTIONS FROM DWUCK [2] CALCULATIONS. EXTENSIVE
COMPARISONS WITH EXPERIMENTAL DATA USED IN THE EVALUATION
PROCESS ARE SHOWN IN [5]
3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM (TNG
CALCULATED). GUIDANCE FROM (N,XN) EMISSION DATA [5].
3-102 (N,G) DATA TAKEN FROM RESONANCE PARAMETERS FROM 1.E-5 EVTO
99.5 KEV. A SMALL BACKGROUND IS GIVEN HERE WHICH WHEN
ADDED TO THE RESONACE CONTRIBUTION REPRODUCES EXPERIMENTAL
DATA,INCLUDING THE THERMAL VALUE OF 4.50B. V5 DATA FROM
99.5 KEV TO 20.0 MEV WERE REPLACED BY POINTS ON A CURVE
DRAWN THROUGH DATA FROM THE CSISRS LIBRARY [5,13]; RESULTS
COMPARABLE TO EYE GUIDE IN REF [14].
3-103 (N,P) CROSS SECTIONS WERE CALCULATED BY THE TNG
CODE [3,4,5].
3-104 (N,D) CROSS SECTION - SHAPE OF (N,P) CROSS SECTION USED
NORMALIZED TO AVAILABLE DATA [5].
3-106 (N,3HE) CROSS SECTION - SHAPE OF (N,A) CROSS SECTION
USED NORMALIZED TO AVAILABLE DATA [15].
3-107 (N,A) CROSS SECTIONS WERE TAKEN FROM THE GLUCS [11]
CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL-
TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS
SECTIONS [12].
4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR
ELASTIC SCATTERING ARE RESULTS OF FITTING DATA WITH GENOA.
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 62CU RESIDUAL, AND ENERGY DEPENDENT YIELD
BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA
RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR
EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR
THE OUTGOING NEUTRON). (N,XN) AND (N,XG) D-D EMISSION
DATA HEAVILY USED TO BENCHMARK THE TNG CALCULATIONS [5].
6-22 (N,NA) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE
NEUTRON, ALPHA, AND 59CO RESIDUAL, AND ENERGY DEPENDENT
YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE
GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN
FOR EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY
FOR THE OUTGOING NEUTRON). (N,XA) AND (N,XG) D-D EMISSION
DATA HEAVILY USED TO BENCHMARK THE TNG CALCULATIONS [5].
6-28 (N,NP) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE
NEUTRON AND 62NI RESIDUAL, AND ENERGY DEPENDENT YIELD
BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA
RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR
EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR
THE OUTGOING NEUTRON). (N,XP) AND (N,XG) D-D EMISSION
DATA HEAVILY USED TO BENCHMARK THE TNG CALCULATIONS [5].
6-51 THROUGH 6-72 INELASTIC SCATTERING EXCITING LEVELS; EACH
SECTION INCLUDES SIMPLE CONSTANT YIELDS FOR THE NEUTRON
AND 63CU RESIDUAL; ANGULAR DISTRIBUTIONS ARE GIVEN FOR
THE OUTGOING NEUTRON (LEGENDRE COEFFICIENTS COMPUTED
BY DWUCK [2] AND TNG [3,4,5]). EXTENSIVE COMPARISONS
WITH ANGULAR DISTRIBUTION DATA ARE GIVEN IN REF. [5]
6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES
SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 63CU
RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG
CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; CALCULATED
NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH (ANGULAR
DISTRIBUTIONS ARE GIVEN ONLY FOR THE OUTGOING NEUTRON).
(N,XN) AND (N,XG) D-D EMISSION DATA HEAVILY USED TO BENCH-
MARK THE TNG CALCULATIONS [5].
6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P
AND 63NI RESIDUAL, AND ENERGY DEPENDENT YIELD BASED
ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY;
CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH
PRODUCT. (N,XP) AND (N,XG) D-D EMISSION DATA USED TO
BENCHMARK THE TNG CALCULATIONS [5].
6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A
AND 60CO RESIDUAL, AND ENERGY DEPENDENT YIELD BASED
ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY;
CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH
PRODUCT. (N,XA) AND (N,XG) D-D EMISSION DATA USED TO
BENCHMARK THE TNG CALCULATIONS [5].
12-51 THROUGH 12-72 BRANCHING RATIOS FOR THE LEVELS, COMPILED
BY HETRICK ET AL. [5] ARE GIVEN.
12-102 (N,G) CAPTURE; THERMAL VALUES TAKEN FROM DELFINI ET AL.
[16]. HIGHER-ENERGY VALUES BASED ON TNG CALCULATIONS
USING PRIMARY BRANCHING RATIOS OF DELFINI ET AL. FOR
S-WAVES
14-51 THROUGH 14-72 GAMMA-RAY ANGULAR DISTRIBUTIONS ASSUMED TO
BE ISOTROPIC.
14-102 (N,G) CAPTURE; ISOTROPIC DISTRIBUTIONS ASSUMED
15-102 (N,G) CAPTURE; AS IN 12-102
----------------------------------------------------------------
UNCERTAINTY FILES
ALL NON-DERIVED FILES CONTAIN AN LB=8 COMPONENT, AS
REQUIRED BY ENDF/B-VI FORMATS
33-1 TOTAL UNCERTAINTIES GIVEN AS DERIVED FROM 1E-5 TO 200 EV
EXPLICIT FROM 200 EV TO 20 MEV, USING LB=0,1 AND 8.
33-2 EXPLICIT FROM 1E-5 T0 200 EV, DERIVED FROM 200EV TO 20 MEV
33-3 DERIVED FROM 1.E-5 TO 99.5 KEV, EXPLICIT USING LB=1,8 FROM
99.5 KEV TO 20 MEV.
33-4 DERIVED FROM THRESHOLD TO 20 MEV.
33-16 (N,2N) COVARIANCES WERE TAKEN FROM THE GLUCS [11]
CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL-
TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS
SECTIONS [12].
33-22 (N,NA) UNCERTAINTIES ESTIMATED FROM TNG CALCULATION.
33-28 (N,NP) COVARIANCES ESTIMATED FROM TNG CALCULATION.
33-51-91 INELASTIC SCATTERING UNCERTAINTIES ESTIMATED FROM DATA
AND CALCULATIONS.
33-102 CAPTURE UNCERTAINTIES ESTIMATED FROM THERMAL VALUE AT LOW
ENERGIES, BINNED DATA IN THE RESONANCE REGION, AND CSISRS
DATA [5,13,14] FROM 99.5 KEV TO 20 MEV.
33-103 (N,P) COVARIANCES - ESTIMATED AS NO DATA AVAILABLE.
33-104 (N,D) COVARIANCES - ESTIMATED, BASED ON DATA.
33-106 (N,3HE) COVARIANCES - ESTIMATED, BASED ON DATA.
33-107 (N,A) COVARIANCES WERE TAKEN FROM THE GLUCS [11]
CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL-
TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS
SECTIONS [12].
****************************************************************
REFERENCES:
[1] F.G. Perey, computer code GENOA, ORNL, unpublished (1967)
[2] P.D. Kunz, "Distorted Wave Code DWUCK72," Univ. of
Colorado, unpublished (1972)
[3] C.Y. Fu, report ORNL/TM-7042 (1980); also, C.Y Fu,
Symp. on Neutron Cross Sections from 10 to 50 MeV, Upton, NY,
May 1980, Brookhaven National Lab. report BNL-NCS-51245
(1980) p.675
[4] K. Shibata and C.Y. Fu, report ORNL/TM-10093 (1986)
[5] D.M. Hetrick, C.Y. Fu, and D.C. Larson, Oak Ridge report
ORNL/TM-9083 [ENDF-337] (1984)
[6] 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)
[7] M.S. Pandey, J.B. Garg and J.A. Harvey, Phys.Rev. C 15, 600
(1977), and private communication.
[8] F.G. Perey, private communication (1977)
[9] D.C. Larson, Symp. on Neutron Cross Sections from 10 to 50
MeV, Upton, NY, May 1980, Brookhaven National Lab. report
BNL-NCS-51245 (1980) p.277
[10] P. Guenther, D.L. Smith, A.B. Smith and J.F. Whalen, Nucl.
Phys. A, 448, 280 (1986) [CSISRS data set 12869/002], and
W.P. Poenitz and J.F. Whalen, Argonne report ANL/NDM-80
(1983) [CSISRS data set 12853]
[11] D.M. Hetrick and C.Y. Fu, Oak Ridge report ORNL/TM-7341
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