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9.825100+4 2.489230+2 1 1 2 0
0.000000+0 1.000000+0 0 0 0 6
1.000000+0 2.000000+7 0 0 10 31
0.000000+0 0.000000+0 0 0 133 1
98-Cf-251 NEA RCOM-JUN82 SCIENTIFIC CO-ORDINATION GROUP
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 9858
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
******************************************************************
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 (MF1 MT452,455,456)
******************************************************************
******************************************************************
* JEF-2 *
* DATA WERE TAKEN FROM ENDF/B-V(MAT=8851). *
******************************************************************
* 3-JAN-85: RADIOACTIVE DECAY DATA DELETED.
* 10-JUN-86: ISOTROPIC MF=4,MT=18 ADDED.
* 7-APR-88: CHANGE OF THE FLAG FROM SINGLE LEVEL TO MULTI LEVEL
* BREIT-WIGNER RESONANCE PARAMETERS.FOR THE SPIN OF
* L=0,RESONANCES HAVE BEEN RANDOMLY ASSIGNED BY THE
* COMPUTER CODE RNDSPIN (H. GRUPPELAAR)
******************************************************************
BNL,SRL,LLLEVAL-JUL76 KINSEY-ASSEMBLER(SEE COMMENTS)
DIST-DEC78 790307
THIS EVALUATION IS IN GENERAL A COMBINATION OF THE AUGUST
1975 EVALUATION OF BENJAMIN AND MCCROSSON AT SRL DOCUMENTED HERE
AND THE ENDL EVALUATION OF HOWERTON AT LLL (REF.3). BOTH SOURCES
WERE MODIFIED TO CONFORM TO THE ENDF/B-V FORMAT REQUIREMENTS.
IMPORTANT CHANGES OR ADDITIONS ARE NOTED.
MF=1 GENERAL INFORMATION
MT=452 NUBAR THERMAL VALUE COMPUTED FROM SEMI-EMPIRICAL WORK
OF GORDEEVA AND SMIRENKIN(REF.1) AS REVISED BY MANERO AND
KONSHIN(REF.2). ENERGY DEPENDENCE BASED ON WORK OF HOWER-
TON(REF.3) RENORMALIZED TO THE THERMAL VALUE AT BNL.
MF=2 RESONANCE PARAMETERS(0 TO 10 KEV)
MT=151 RESOLVED RESONANCES RESONANCE PARAMETERS DETERMINED BY
THE GENRPAR CODE(REF.4) BASED UPON RESONANCE INTEGRALS AND
CROSS SECTIONS FROM PRODUCTION MEASUREMENTS(REF.5) AND ORR
IRRADIATIONS(REF.6). RESOLVED REGION - 0 TO 163.9 EV.
UNRESOLVED RESONANCES SAME BASIS AS RESOLVED, WITH
AVERAGE RESONANCE PARAMETERS. UNRESOLVED REGION - 163.9 EV
TO 10 KEV.
NOTE: A BOUND LEVEL AT -2.035 EV WAS REMOVED FROM THE SRL
EVALUATION. APPRORIATE BACKGROUNDS WERE INCLUDED IN MF=3
IN ORDER THAT THE NG AND NF CURVES WOULD REMAIN THE SAME.
CROSS SECTION SIGMA(0.0253 EV) I(0.5 EV - 20 MEV)
TOTAL 8191.73
ELASTIC 8.84
FISSION 5321.28 4949.63
CAPTURE 2861.61 1629.34
MF=3 SMOOTH CROSS SECTIONS(1.-5 EV TO 20 MEV)
MT=1 SUM OF THE ELASTIC, NF, AND NG BACKGROUND FILES UP TO 10
KEV JOINED TO THE LLL EVALUATION.
MT=2 BACKGROUND IS A CONSTANT UP TO THE FIRST RESONANCE
WHICH THEN GOES RAPIDLY TO ZERO. CONSTANT CHOSEN TO GIVE
A THERMAL CROSS SECTION IN COMBINATION WITH THE RESONANCE
PARAMETERS WHICH IS EQUAL TO 90( OF THE SPHERICAL OPTICAL
MODEL VALUE. ABOVE 10 KEV THE CROSS SECTION IS FROM THE
LLL EVALUATION.
MT=18,102 BACKGROUND WAS CALCULATED TO GIVE THE SAME CURVE
AFTER THE BOUND LEVEL WAS DELETED AS WAS OBTAINED WITH THE
ORIGINAL SRL PARAMETERS UP TO 10 KEV JOINED TO THE
LLL EVALUATION.
MT=4,91 FROM LLL EVALUATION WITH Q CALCULATED FROM THRESHOLD.
MT=16,17,37 FROM LLL EVALUATION WITH THRESHOLD CALCULATED FROM
THE Q VALUE.
MT=251,252,253 CALCULATED AT BNL.
MF=4 ANGULAR DISTRIBUTIONS
MT=2 ELASTIC FROM LLL EVALUATION CULLED TO 101 POINTS PER
DISTRIBUTION AND RENORMALIZED.
MT=16,17,37,91 DUMMY ISOTROPIC DISTRIBUTIONS.
MF=5 SECONDARY NEUTRON ENERGY DISTRIBUTIONS
MT=16,17,37,91 FROM LLL EVALUATION.
MT=18 SIMPLE FISSION MAXWELLIAN WITH ENERGY DEPENDENT TEMPER-
ATURE FROM THE SRL EVALUATION.
REFERENCES
1. L.D.GORDEEVA AND G.N.SMIRENKIN,SOV.AT.EN.14(1963)56.
2. F.MANERO AND V.A.KONSHIN,AT.EN.REV.10(1972)637.
3. R.J.HOWERTON, UCRL 50400, VOL. 15, PART A (METHODS) SEPT 75
AND PART B (CURVES) APR 76.
4. F.J.MCCROSSON,PROC.CONF.NEUT.CROSS SECTIONS AND TECH.,
KNOXVILLE,TN,MARCH 1971,P.714.
5. R.W.BENJAMIN,F.J.MCCROSSON,V.D.VANDERVELDE, AND T.C.GORRELL,
USERDA REPORT DP-1394(1975).
6. J.HALPERIN,C.E.BEMIS,R.E.DRUSCHEL,AND R.E.EBY,USAEC REPORT
ORNL-4706(1971)47.
******************************************************************
Relevant comments from ENDF/B-VI.4
----------------------------------
ENDF/B-VI REVISION 1
ADDED MISSING FISSION NEUTRON ANGULAR DISTRIBUTION MF=4 MT=18
ASSUMED TO BE ISOTROPIC
* *
ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC
* * * * * * *
THIS EVALUATION IS IN GENERAL A COMBINATION OF THE AUGUST
1975 EVALUATION OF BENJAMIN AND MCCROSSON AT SRL DOCUMENTED HERE
AND THE ENDL EVALUATION OF HOWERTON AT LLNL (REF.3). BOTH SOURCES
WERE MODIFIED TO CONFORM TO THE ENDF/B-V FORMAT REQUIREMENTS.
IMPORTANT CHANGES OR ADDITIONS ARE NOTED.
MF=1 GENERAL INFORMATION
MT=452 NUBAR THERMAL VALUE COMPUTED FROM SEMI-EMPIRICAL WORK
OF GORDEEVA AND SMIRENKIN(REF.1) AS REVISED BY MANERO AND
KONSHIN(REF.2). ENERGY DEPENDENCE BASED ON WORK OF HOWER-
TON(REF.3) RENORMALIZED TO THE THERMAL VALUE AT BNL.
MT=455 DEL. NUBAR, M.C.BRADY AND T.R.ENGLAND, NSE 103,129(1989)
REFERENCES
1. L.D.GORDEEVA AND G.N.SMIRENKIN,SOV.AT.EN.14(1963)56.
2. F.MANERO AND V.A.KONSHIN,AT.EN.REV.10(1972)637.
3. R.J.HOWERTON, UCRL 50400, VOL. 15, PART A (METHODS) SEPT 75
AND PART B (CURVES) APR 76.
4. F.J.MCCROSSON,PROC.CONF.NEUT.CROSS SECTIONS AND TECH.,
KNOXVILLE,TN,MARCH 1971,P.714.
5. R.W.BENJAMIN,F.J.MCCROSSON,V.D.VANDERVELDE, AND T.C.GORRELL,
USERDA REPORT DP-1394(1975).
6. J.HALPERIN,C.E.BEMIS,R.E.DRUSCHEL,AND R.E.EBY,USAEC REPORT
ORNL-4706(1971)47.
******************************************************************
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