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9.424300+4 2.409740+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 77 1
94-Pu-243 NEA RCOM-JUN82 SCIENTIFIC CO-ORDINATION GROUP
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 9449
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
******************************************************************
***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- JEF-2.2 (DIST-JAN92)
******************************************************************
******************************************************************
* JEF-2 *
* DATA WERE TAKEN FROM ENDF/B-V(MAT=8443). *
******************************************************************
* 21-DEC-84: RADIOACTIVE DECAY DATA DELETED.
* 10-JUN-86: ISOTROPIC MF=4,MT=18 ADDED.
* 5-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.5). 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).
MF=2 RESONANCE PARAMETERS(0 TO 10 KEV)
MT=151 RESOLVED RESONANCES RESONANCE PARAMETERS DETERMINED BY
THE GENRPAR CODE(REF.3) BASED ON THE ESTIMATED RESONANCE
INTEGRALS AND THERMAL CROSS SECTIONS FROM PRODUCTION STUDIES
(REF.4). RESOLVED REGION - 0 TO 101.7 EV.
UNRESOLVED RESONANCES CONTINUATION WITH AVERAGE PARA-
METERS BY GENRPAR. UNRESOLVED REGION - 101.7 EV TO 10 KEV.
CROSS SECTION SIGMA(0.0253 EV) I(0.5 EV - 20 MEV)
TOTAL 289.252
ELASTIC 19.752
FISSION 181.394 557.436
CAPTURE 88.106 274.163
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. F.J.MCCROSSON,PROC.3RD CONF.NEUT.CROSS SECT.AND TECH.,
KNOXVILLE,TN,MARCH 1971,P.714.
4. R.W.BENJAMIN,F.J.MCCROSSON,V.D.VANDERVELDE,AND T.C.GORRELL,
USERDA REPORT DP-1394(1975).
5. R. HOWERTON, UCRL 50400, VOL 15, PART A, SEPT 75 (METHODS)
AND PART B, APR 76 (CURVES).
1 451 82
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