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94-Pu-244 NEA RCOM-JUN82 SCIENTIFIC CO-ORDINATION GROUP DIST-JAN09 20090105 ----JEFF-311 MATERIAL 9452 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT *************************** JEFF-3.1.1 ************************* ** ** ** Original data taken from: JEFF-3.1 ** ** ** ****************************************************************** ***************************** JEFF-3.1 ************************* ** ** ** Original data taken from: JEFF-3.0 ** ** ** ****************************************************************** ***************************** JEFF-3.0 *********************** DATA TAKEN FROM :- JEF-2.2 (DIST-JAN92) Components of the energy released by fission (MT=458) updated by O. Serot et al. (JEF/DOC-887). Fission Q updated consistently. ****************************************************************** ****************************************************************** * JEF-2 * * DATA WERE TAKEN FROM ENDF/B-V(MAT=8444). * ****************************************************************** * 21-DEC-84: RADIOACTIVE DECAY DATA DELETED. * 3-DEC-85: RESONANCE PARAM. CHANGED TO ORIGINAL SINGLE-LEVEL. * 5-APR-88: CHANGE OF THE FLAG FROM SINGLE LEVEL TO MULTI LEVEL * BREIT-WIGNER RESONANCE PARAMETERS ****************************************************************** HEDL,SRL EVAL-APR78 MANN,SCHENTER,BENJAMIN,MCCROSSON HEDL TME 77-54 DIST-DEC78 790307 HEDL EVAL-APR78 MANN AND SCHENTER (FAST) SRL EVAL-AUG75-BENJAMIN AND MCCROSSON (THERMAL) INEL EVAL-AUG78 REICH (DECAY) MF=1 GENERAL INFORMATION MT=452 NU BASED ON WORK OF HOWERTON (REF. 5) MT=458 ENERGY OF FISSION. SYSTEMATICS OF SHER (REF.6) MF=2 RESONANCE PARAMETERS(0 TO 10 KEV) MT=151 RESOLVED RESONANCES RESONANCE PARAMETERS DETERMINED BY THE GENRPAR CODE(REF.4) BASED ON THE SRL DATA SET. RESOLVED REGION - 0 TO 249.2 EV. UNRESOLVED RESONANCES SAME BASIS AS RESOLVED, WITH AVERAGE RESONANCE PARAMETERS. UNRESOLVED REGION - 249.2 EV TO 10 KEV. MF=3 SMOOTH CROSS SECTIONS(0 TO 20 MEV) MT=1 TOTAL SUM OF PARTIAL CROSS SECTIONS MT=2 ELASTIC OPTICAL MODEL CALCULATIONS (REF. 1) MT=4 INELASTIC STATISTICAL MODEL CALCULATION USING 5 EXCITED LEVELS AND CONTINUUM (REF. 1) MT=16 N,2N BASED ON STATISTICAL MODEL CALCULATIONS (REF. 1) MT=17 N,3N BASED ON STATISTICAL MODEL CALCULATIONS (REF. 1) MT=18 FISSION STATISTICAL MODEL CALCULATION BASED ON THE DATA OF BEHRENS AND BROWNE (REF 2) MT=19 (N,F) SAME AS MT=18 UNTIL (N,NF) THRESHOLD, CONSTANT THEREAFTER. MT=20 (N,NF) DIFFERENCE BETWEEN MT=18 AND MT=19 MT=37 N,4N SAME AS MT=17 MT=51,...,55,91 INELASTIC STATISTICAL MODEL CALCULATION USING 5 EXCITED LEVELS AND CONTINUUM (REF. 1) MT=102 CAPTURE STATISTICAL MODEL CALCULATION (REF. 1) MT=251,252,253 BASED ON MF=4, MT=2 MF=4 ANGULAR DISTRIBUTIONS MT=2 ELASTIC BASED ON STATISTICAL MODEL CALCULATIONS MT%2 ASSUMED ISOTROPIC MF=5 ENERGY DISTRIBUTIONS MT=16 BASED ON GILBERT AND CAMERON MT=17 SAME REFERENCE AS MT=16 MT=18,19,20 MAXWELLIAN DESCRIPTION MT=37 SAME REFERENCE AS MT=16 MT=91 BASED ON GILBERT AND CAMERON (REF. 3) REFERENCES 1. F.M.MANN AND R.E. SCHENTER, TRANS.AMER.NUC.SOC. 23(1976)546 AND HEDL TME 77-54 (1977) 2. BEHRENS AND BROWNE - LLL (P.C.) 3. A. GILBERT AND A.G.W. CAMERON, CAN.J.PHYS. 43(1965)1446 4. F.J.MCCROSSON,PROC.CONF.NEUT.CROSS SECTIONS AND TECH., KNOXVILLE,TN,MARCH 2971,P.714. 5. R.J. HOWERTON NUCL.SCI.ENG. 62(1977)438. 6. R. SHER, S. FIARMAN, AND C. BECK (PRIV. COMM., OCT. 1976)Back |