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93-Np-238 NEA RCOM-JUN82 SCIENTIFIC CO-ORDINATION GROUP DIST-JAN09 20090105 ----JEFF-311 MATERIAL 9349 -----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 ** ** ** ****************************************************************** 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 (MF1MT452,455,456 MF5MT455) ****************************************************************** ****************************************************************** * JEF-2 * * DATA WERE TAKEN FROM ENDF/B-V(MAT=8338). * ****************************************************************** * 21-DEC-84: RADIOACTIVE DECAY DATA DELETED. * 28-AUG-85: MISSING ISOTROPIC ANG. DISTR. FOR FISSION INSERTED * 30-OCT-86: CROSS SECTION DATA ABOVE 10 KEV AND ALL MT=4,16,17 * AND 91 REPLACED BY DATA FROM THE ENDL84 LIBRARY. * 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) ****************************************************************** SRL EVAL-AUG75-BENJAMIN AND MCCROSSON DIST-DEC78 790307 FILES CONVERTED TO ENDF/B-V FORMAT AND DECAY DATA MERGED AT BNL BY R. KINSEY * * * * * * NEPTUNIUM-238 EVALUATION AUGUST 1975 - R.W.BENJAMIN AND F.J.MCCROSSON AT SRL 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.4) BASED UPON THE SRL DATA SET AND AN AVERAGE LEVEL SPACING OF 1.05 EV. RESOLVED REGION - 0 TO 100.2 EV. UNRESOLVED RESONANCES SAME BASIS AS RESOLVED WITH AVERAGE RESONANCE PARAMETERS. UNRESOLVED REGION - 100.2 EV TO 10 KEV. CROSS SECTION SIGMA(0.0253 EV) I(0.5 EV - 20 MEV) TOTAL 2250.99 ELASTIC 21.25 FISSION 2026.90 895.60 CAPTURE 202.83 100.03 MF=3 SMOOTH CROSS SECTIONS(0 TO 20 MEV) *** THE DATA IN FILE 3 ARE GIVEN ONLY SO THAT THE VARIOUS PROCESSING CODES CAN WORK. CONTINUITY WITH THE UNRESOLVED REGION IS PROVIDED, BUT THE CROSS SECTIONS DROP IMMEDIATELY TO ZERO. THE ELASTIC SCATTERING CROSS SECTION ABOVE 10 KEV IS THE POTENTIAL SCATTERING CROSS SECTION CALCULATED WITH A SPHERICAL OPTICAL MODEL POTENTIAL AT 10 KEV. MF=4 ANGULAR DISTRIBUTIONS MT=2 ELASTIC DISTRIBUTIONS TAKEN FROM ENDF/B-V U-238 MF=5 SECONDARY NEUTRON ENERGY DISTRIBUTIONS MT=18 FISSION SIMPLE FISSION MAXWELLIAN WITH ENERGY-DEPENDENT TEMPERATURE. 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,NUCL.SCI.ENG.46(1971)42. 4. F.J.MCCROSSON,PROC.CONF.NEUT.CROSS SECTIONS AND TECH., KNOXVILLE,TN,MARCH 1971,P.714. ****************************************************************** Relevant comments from ENDF/B-VI.4 ---------------------------------- ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC * * * * * * * FILES CONVERTED TO ENDF/B-V FORMAT AND DECAY DATA MERGED AT BNL BY R. KINSEY * * * * * * NEPTUNIUM-238 EVALUATION AUGUST 1975 - R.W.BENJAMIN AND F.J.MCCROSSON AT SRL 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 HOWERTON (REF.3) MT=455 DEL. NUBAR, M.C.BRADY AND T.R.ENGLAND, NSE 103,129(1989) MF=5 SECONDARY NEUTRON ENERGY DISTRIBUTIONS 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,NUCL.SCI.ENG.46(1971)42. 4. F.J.MCCROSSON,PROC.CONF.NEUT.CROSS SECTIONS AND TECH., KNOXVILLE,TN,MARCH 1971,P.714. ******************************************************************Back |