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96-Cm-248 JAERI EVAL-MAR84 Y.KIKUCHI AND T.NAKAGAWA DIST-JAN09 20090105 ----JEFF-311 MATERIAL 9649 -----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 :- JENDL-3.2 (DIST-SEP89) JAERI-M 84-116 JEF-2.2 (MF12-MF15) Adopt the same LNU=2 representation for neutron multiplicities Components of the energy released by fission (MT=458) updated by O. Serot et al. (JEF/DOC-887). Fission Q updated consistently. ****************************************************************** HISTORY 84-03 NEW EVALUATION FOR JENDL-3 WAS MADE BY Y.KIKUCHI AND T.NAKAGAWA (JAERI). DETAILS ARE GIVEN IN REF. /1/. MF=1 GENERAL INFORMATION MT=451 COMMENTS AND DICTIONARY MT=452 NUMBER OF NEUTRONS PER FISSION SUM OF MT=455 AND MT=456. MT=455 NUMBER OF DELAYED NEUTRONS PER FISSION SEMI-EMPIRICAL FORMULA BY TUTTLE /2/. MT=456 NUMBER OF NEUTRONS PER FISSION SEMI-EMPIRICAL FORMULA BY HOWERTON /3/. MF=2 RESONANCE PARAMETERS MT=151 RESONANCE PARAMETERS RESOLVED RESONANCE REGION (MLBW) : 1.0E-5 TO 1.5 KEV RESONANCE ENERGIES, NEUTRON AND RADIATIVE WIDTHS WERE TAKEN FROM THE EXPERIMENTAL DATA OF BENJAMIN ET AL./4/. FOR RESONANCES WHOSE RADIATIVE WIDTH WAS UNKNOWN, THE AVERAGE VALUE OF 0.026 EV /4/ WAS ADOPTED. FISSION WIDTHS AND THE AVERAGE FISSION WIDTH OF 0.0013 EV WERE ADOPTED FROM MOORE AND KEYWORTH /5/. THE AVERAGE FISSION WIDTH WAS USED FOR ALL RESONANCES OF WHICH FISSION WIDTH HAD NOT BEEN MEASURED. R=9.1 FM WAS ASSUMED TO REPRODUCE THE POTENTIAL SCATTERING CROSS SECTION OF 10.4 BARNS ASSUMED BY BENJAMIN ET AL./4/. THE NEUTRON WIDTH OF THE FIRST RESONANCE WAS SLIGHTLY ADJUSTED TO REPRODUCE THE CAPTURE CROSS SECTION OF 2.57 BARNS AT 0.0253 EV. BACKGROUND CROSS SECTIONS WERE GIVEN ONLY FOR THE FISSION AND TOTAL CROSS SECTIONS BY ASSUMING THE FORM OF 1/V. THE THERMAL CROSS SECTIONS TO BE REPRODUCED WERE ESTIMATED FROM AVAILABLE EXPERIMENTAL DATA. UNRESOLVED RESONANCE REGION : 1.5 KEV TO 30 KEV OBTAINED FROM OPTICAL MODEL CALCULATION: S1=3.32E-4, S2=0.844E-4, R=8.88 FM. ESTIMATED FROM RESOLVED RESONANCES: D-OBS=40.0 EV, GAM-G=26 MILLI-EV, S0=1.2E-4 GAM-F OBTAINED BY FITTING THE DATA OF STOPA ET AL./6/. CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS 2200 M/S VALUE RES. INT. TOTAL 9.455 B - ELASTIC 6.514 B - FISSION 0.370 B 17.5 B CAPTURE 2.570 B 260. B MF=3 NEUTRON CROSS SECTIONS BELOW 30 KEV, CROSS SECTIONS WERE REPRESENTED WITH RESONANCE PARAMETERS. MT=1,2,4,51-58,91,102,251 TOTAL, ELASTIC AND INELASTIC SCATTERING, CAPTURE CROSS SECTIONS AND MU-L CALCULATED WITH OPTICAL AND STATISTICAL MODEL CODE CASTHY/7/. THE SPHERICAL OPTICAL POTENTIAL PARAMETERS (MEV,FM): V =43.4-0.107*EN, R =1.282, A =0.60 WS =6.95-0.339*EN+0.0531*EN**2, RS =1.29, B =0.50 (DERIVATIVE WOODS-SAXON FORM) VSO=7.0, RSO=1.282, ASO=0.60 THIS SET OF POTENTIAL PARAMETERS WAS DETERMINED /8/ TO REPRODUCE WELL THE TOTAL CROSS SECTION OF AM-241 BY PHILLIPS AND HOWE /9/. IN THE STATISTICAL MODEL CALCULATION, COMPETING PROCESSES OF FISSION, (N,2N), (N,3N) AND (N,4N), AND LEVEL FLUCTUATION WERE CONSIDERED. THE LEVEL SCHEME OF CM-248 WAS TAKEN FROM REF./10/. NO. ENERGY(KEV) SPIN-PARITY G.S. 0 0 + 1 43.40 2 + 2 143.6 4 + 3 297 6 + 4 510 8 + 5 1048 2 + 6 1050 1 - 7 1084 0 + 8 1094 3 - CONTINUUM LEVELS ASSUMED ABOVE 1126 KEV. THE LEVEL DENSITY PARAMETERS : GILBERT AND CAMERON /11/. GAMMA-RAY STRENGTH FUNCTION OF 6.5E-4 DEDUCED FROM RESONANCE PARAMETERS. MT=16,17,37 (N,2N), (N,3N) AND (N,4N) REACTION CROSS SECTIONS CALCULATED WITH EVAPORATION MODEL/12/. MT=18 FISSION EVALUATED ON THE BASIS OF THE MEASURED DATA BY STOPA ET AL./6/ AND FOMUSHKIN ET AL./13/. MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS MT=2,51-58 CALCULATED WITH OPTICAL MODEL. MT=16,17,18,37,91 ISOTROPIC IN THE LABORATORY SYSTEM. MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS MT=16,17,37,91 EVAPORATION SPECTRUM. MT=18 MAXWELLIAN FISSION SPECTRUM. TEMPERATURE ESTIMATED FROM SYSTEMATICS OF SMITH ET AL./14/. REFERENCES 1) KIKUCHI Y. AND NAKAGAWA T.: JAERI-M 84-116 (1984). 2) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, 29 (1979). 3) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438(1977). 4) BENJAMIN R.W. ET AL.: NUCL. SCI. ENG., 55, 440(1974). 5) MOORE M.S. AND KEYWORTH G.A.: PHYS. REV., C3, 1656(1971) 6) STOPA C.R.S. ET AL.: 1982 KIAMESHA, 1090 (1982), AND MAGUIRE JR. H.T. ET AL.: NUCL. SCI. ENG., 89, 293 (1985). 7) IGARASI S.: J. NUCL. SCI. TECHNOL., 12, 67 (1975). 8) IGARASI S. AND NAKAGAWA T.: JAERI-M 8342 (1979). 9) PHILLIPS T.W. AND HOWE F.R.: NUCL. SCI. ENG., 69, 375(1979). 10) LEDERER C.M. AND SHIRLEY V.S.: TABLE OF ISOTOPES , 7TH ED. (1978). 11) GILBERT A. AND CAMERON A.G.W.: CAN. J. PHYS., 43, 1446(1965). 12) PEARLSTEIN S.: NUCL. SCI. ENG., 23, 238 (1965). 13) FOMUSHKIN E.F. ET AL.: SOV. J. NUCL. PHYS., 31, 19(1980). 14) SMITH A.B. ET AL.: ANL/NDM-50 (1979). ****************************************************************** Relevant comments from JEF-2.2 ------------------------------ * JEF-2 * * DATA WERE TAKEN FROM ENDF/B-V(MAT=8648). * * * * 19-AUG-84: AWR NUMBER CORRECTED IN MF=2,MT=151 * 2-JAN-85: RADIOACTIVE DECAY DATA DELETED. * 6-APR-88: CHANGE OF THE FLAG FROM SINGLE LEVEL TO MULTI LEVEL * BREIT-WIGNER RESONANCE PARAMETERS * * HEDLSRLLLL EVAL-APR78 MANN,BENJAMIN,HOWERTON,ET AL. HEDL TME 77-54 DIST-DEC78 790307 HEDL EVAL-APR78 MANN AND SCHENTER (FAST) SRL EVAL-APR74 R.W.BENJAMIN (THERMAL) LLL EVAL-APR78 HOWERTON (GAMMA PRODUCTION) INEL EVAL-AUG78 REICH (DECAY) MF=1 GENERAL INFORMATION MT=458 ENERGY OF FISSION. SYSTEMATICS OF SHER (REF.13) MF=12,13,14,15 PHOTON PRODUCTION FILES TAKEN FROM THE LLL EVALUATIONS OF R. HOWERTON DOCUMENTED IN UCRL 50400, VOL. 15, PART A (METHODS) SEPT 75 AND PART B (CURVES) APR 76. FILES EXTENDED TO THE ENERGY RANGE 1.-5 EV TO 20 MEV AND MERGED TO THIS EVALUATION AT BNL BY R. KINSEY. 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. R.W.BENJAMIN,C.E.AHLFELD,J.A.HARVEY AND N.W.HILL,NUCL.SCI. ENG.55(1974)440. 5. M.S.MOORE AND G.A.KEYWORTH,PHYS.REV.C3(1971)1658. 6. R.W.BENJAMIN,K.W.MACMURDO AND J.D.SPENCER,NUCL.SCI.ENG. 47(1972)203. 7. R.E.DRUSCHEL,R.D.BAYBARZ,AND J.HALPERIN,ORNL-4891)23. 8. R.W.BENJAMIN,F.J.MCCROSSON,V.D.VANDERVELDE,AND T.C.GORRELL, USERDA REPORT DP-1394(1975). 10. F. M. MANN AND R.E. SCHENTER, TRANS.AMER.NUC.SOC. 23(1976)546 AND TO BE PUBLISHED AND HEDL TME 77-54 (1977) 11. S. PEARLSTEIN BNL 897 (1964) 12. C. DUNFORD AND H. ALTER NAA-SR-12271 (1967) 13. R. SHER, S. FIARMAN, AND C. BECK (PRIV. COMM., OCT. 1976) 14. A. GILBERT AND A.G.W. CAMERON CAN.J.PHYS. 43(1965)1446 ******************************************************************Back |