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98-Cf-252 NEA RCOM-JUN82 SCIENTIFIC CO-ORDINATION GROUP
DIST-JAN09 20090105
----JEFF-311 MATERIAL 9861
-----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: JEFF-3.0 **
** **
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***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- JEF-2.2 (DIST-JAN92)
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* JEF-2 *
* DATA WERE TAKEN FROM ENDF/B-V(MAT=8852). *
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* 3-JAN-85: RADIOACTIVE DECAY DATA AND FISSION YIELD 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
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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 (REFS.6 + 7). RESOLVED REGION - 0 TO 366.5 EV.
UNRESOLVED RESONANCES SAME BASIS AS RESOLVED, WITH
AVERAGE RESONANCE PARAMETERS. UNRESOLVED REGION - 366.5 EV
TO 10 KEV.
CROSS SECTION SIGMA(0.0253 EV) I(0.5 EV - 20 MEV)
TOTAL 63.881
ELASTIC 11.213
FISSION 32.174 119.198
CAPTURE 20.493 47.292
MF=3 SMOOTH CROSS SECTIONS(1.-5 EV TO 20 MEV)
MT=1,2,18,102 ZERO BACKGROUND FILES 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,J.H.OLIVER,AND R.W.STOUGHTON,USAEC REPORT ORNL-
4706(1971)53.
7. J.HALPERIN,C.E.BEMIS,R.E.DRUSCHEL,AND J.R.STOKELY,NUCL.SCI.
ENG.37(1969)228.
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