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91-Pa-231 NEA RCOM-JUN82 SCIENTIFIC CO-ORDINATION GROUP
DIST-JAN09 20090105
----JEFF-311 MATERIAL 9131
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
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** Original data taken from: JEFF-3.1 **
** **
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***************************** JEFF-3.1 *************************
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** Original data taken from: JEFF-3.0 **
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05-01 NEA/OECD (Rugama) 8 delayed neutron groups
Jefdoc-976 (Wilson and England, Prog Nucl Eng 41,71(2002)
***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- JEF-2.2 (DIST-JAN92)
ENDF/B-VI.4 (MT1MT452,455,456, MF5MT455)
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* JEF-2 *
* DATA WERE TAKEN FROM ENDF/B-V(MAT=8131). *
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* 18-DEC-84: RADIOACTIVE DECAY DATA DELETED.
* 26-DEC-84: Q-VALUE FOR MT=102 CORRECTED
* 31-MAR-88: CHANGE OF THE FLAG FROM SINGLE LEVEL TO MULTI LEVEL
* BREIT-WIGNER RESONANCE PARAMETERS
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HEDL EVAL-NOV77 MANN
DIST-DEC78 790307
MF=1
MT=452 NU. SYSTEMATICS (REF. 4)
MT=458 ENERGY OF FISSION. SYSTEMATICS OF SHER (REF. 5)
MF=2
MT=151 RESOLVED PARAMETERS FROM BNL-325 (REF. 1), EXCEPT FOR
NEGATIVE ENERGY RESONANCE WHERE NEUTRON AND FISSION WIDTHS
CHANGED TO MATCH THERMAL CAPTURE AND FISSION CROSS SECTIONS
(227. B AND .010 B VERSUS 210. +- 20. B AND .010 +- .005 B FROM
BNL-325, RESPECTIVELY). THE CALCULATED CAPTURE RESONANCE
INTEGRAL FROM THE RESOLVED REGION (1237) IS SLIGHTLY LESS
THAN FOR ENTIRE REGION GIVEN IN BNL-325 (1500+-100).
UNRESOLVED PARAMETERS (E=14.3 TO 1000 EV) BASED ON RESOLVED.
MF=3
MT=1 TOTAL. FROM OPTICAL MODEL
MT=2 ELASTIC. DIFFERENCE BETWEEN TOTAL AND SUM OF PARTIALS
MT=4 INELASTIC. SUM OF MT=51,...,62,91
MT=16 (N,2N)
MT=18 FISSION. BASED ON MUIR AND VESSER (REF. 2), LASL BOMB
DATA. LOW ENERGY (.LT. 100 KEV) AND HIGH ENERGY (.GT. 3 MEV)
FROM STATISTICAL MODEL CALCULATIONS (REF. 3).
MT=51,...,62,91 INELASTIC. BASED ON STATISTICAL MODEL
CALCULATIONS (REF. 3).
MT=102 CAPTURE. BASED ON STATISTICAL MODEL CALCULATIONS (REF.
3)
MT=251,252,253. DERIVED FROM MF=4,MT=1
MF=4
MT=1 TOTAL. BASED ON OPTICAL MODEL (POTENTIAL SCATTERING )
MT=16 (N,2N). ASSUMED ISOTROPIC
MT=18 FISSION ASSUMED ISOTROPIC.
MT=51,...,62,91 INELASTIC. ASSUMED ISOTROPIC
MF=5
MT=16 (N,2N). SIMPLE EVAPORATION MODEL
MT=18 FISSION. MAXWELLIAN DISTRIBUTION (T=1.33 MEV)
MT=91 CONTINUUM INELASTIC. SIMPLE EVAPORATION MODEL.
91-PA-231 INEL EVAL-AUG78 REICH
DATA ADD TO THE FILE AT BNL BY R. KINSEY SEP 78.
REFERENCES
1. S.F. MUGHABGHAB AND D.I. GARBER, BNL-325, VOL. 1 (1973),
BROOKHAVEN NATIONAL LABORATORY.
2. D.W. MUIR AND L.R. VESSOR, LA-4648-MS (1971), LOS ALAMOS
SCIENTIFIC LABORATORY
3. F.M. MANN AND R.E. SCHENTER, HEDL-TME-77-54 (1977) HANFORD
4. R.J. HOWERTON, NUCL. SC. AND ENG. 62(1977)438
5. R. SHER (PRIV. COMM., 1977)
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Relevant comments taken from ENDF/B-VI.4
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ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC
* * * * * * *
MF=1
MT=452 NU. SYSTEMATICS (REF. 4),MT=455 BRADY+,NSE 103,129(1989)
MT=458 ENERGY OF FISSION. SYSTEMATICS OF SHER (REF. 5)
MF=5
MT=455 DELAYED NEUT. YIELDS, BRADY,ENGLAND NSE 103,129(1989)
REFERENCES
1. S.F. MUGHABGHAB AND D.I. GARBER, BNL-325, VOL. 1 (1973),
BROOKHAVEN NATIONAL LABORATORY.
2. D.W. MUIR AND L.R. VESSOR, LA-4648-MS (1971), LOS ALAMOS
SCIENTIFIC LABORATORY
3. F.M. MANN AND R.E. SCHENTER, HEDL-TME-77-54 (1977) HANFORD
4. R.J. HOWERTON, NUCL. SC. AND ENG. 62(1977)438
5. R. SHER (PRIV. COMM., 1977)
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