JEFF-3.1 General Purpose Neutron File, May 2005. 2310 0 0 0 9.724700+4 2.449480+2 1 1 2 19746 1451 1 0.000000+0 0.000000+0 0 0 0 69746 1451 2 1.000000+0 2.000000+7 3 0 10 319746 1451 3 0.000000+0 0.000000+0 0 0 177 649746 1451 4 97-Bk-247 JAERI EVAL-JUN95 T.NAKAGAWA AND T.LIU 9746 1451 5 JAERI-RESEARCH 97-056 DIST-MAY05 REV1-MAY05 20050504 9746 1451 6 ----JEFF-31 MATERIAL 9746 9746 1451 7 -----INCIDENT NEUTRON DATA 9746 1451 8 ------ENDF-6 FORMAT 9746 1451 9 ***************************** JEFF-3.1 *************************9746 1451 10 ** **9746 1451 11 ** Original data taken from: JENDL-3.3 **9746 1451 12 ** **9746 1451 13 ******************************************************************9746 1451 14 9746 1451 15 HISTORY 9746 1451 16 95-06 NEW EVALUATION FOR JENDL ACTINIDE FILE WAS MADE BY 9746 1451 17 T.NAKAGAWA AND T.LIU /1/. 9746 1451 18 99-12 RECOMPILED BY T.NAKAGAWA. 9746 1451 19 THE FOLLOWING QUANTITIES ARE RE-EVALUATED AFTER JAERI- 9746 1451 20 RESEARCH 97-056: 9746 1451 21 MF=3 MT=102 DIRECT/SEMI-DIRECT MODIFIED. 9746 1451 22 MF=4 MT= 2 BELOW 500 KEV, REPLACED WITH CASTHY CALC. 9746 1451 23 MF=5 MT=16, 17, 18, 91 9746 1451 24 9746 1451 25 9746 1451 26 MF=1 GENERAL INFORMATION 9746 1451 27 MT=451 COMMENTS AND DICTIONARY 9746 1451 28 MT=452 NUMBER OF NEUTRONS PER FISSION 9746 1451 29 SUM OF MT'S =455 AND 456. 9746 1451 30 MT=455 DELAYED NEUTRON DATA 9746 1451 31 SEMI-EMPIRICAL FORMULA BY TUTTLE /2/. 9746 1451 32 MT=456 PROMPT NEUTRON DATA 9746 1451 33 SEMI-EMPIRICAL FORMULA BY HOWERTON /3/. 9746 1451 34 9746 1451 35 MF=2,MT=151 RESONANCE PARAMETERS 9746 1451 36 RESOLVED RESONANCE REGION (SLBW) : 1.0E-5 TO 150 EV 9746 1451 37 HYPOTHETICAL RESONANCE LEVELS WERE GIVE. THEIR PARAMETERS 9746 1451 38 WERE DETERMINED SO AS TO REPRODUCE THERMAL CROSS SECTIONS. 9746 1451 39 ASSUMED DATA WERE: 9746 1451 40 S-WAVE NEUTRON STRENGTH FUNCTION = 1.0E-4 9746 1451 41 AVERAGE LEVEL SPACING = 2.01 EV (FROM LEVEL DENSITY 9746 1451 42 PARAMETERS) 9746 1451 43 RADIATIVE WIDTH = 0.026 EV /4/ 9746 1451 44 FISSION WIDTH = 0.013 EV (FROM THE RATIO OF CAPTURE 9746 1451 45 AND FISSION CROSS SECTIONS 9746 1451 46 AT THE THERMAL ENERGY) 9746 1451 47 SCATTERING RADIUS = 9.27 FM (CALCULATED WITH OPTICAL 9746 1451 48 MODEL) 9746 1451 49 9746 1451 50 NO UNRESOLVED RESONANCE PARAMETERS WERE GIVEN. 9746 1451 51 9746 1451 52 CALCULATED 2200 M/S CROSS SECTIONS AND RES. INTEGRAL 9746 1451 53 2200 M/S RES. INTEGRAL 9746 1451 54 TOTAL 288.2 B 9746 1451 55 ELASTIC 12.33 B 9746 1451 56 FISSION 91.96 B 453 B 9746 1451 57 CAPTURE 183.9 B 896 B 9746 1451 58 9746 1451 59 MF=3 NEUTRON CROSS SECTIONS 9746 1451 60 CROSS SECTIONS IN THE ENERGY RANGE BELOE 150 EV WERE 9746 1451 61 REPRESENTED WITH RESONANCE PARAMETERS. 9746 1451 62 9746 1451 63 MT=1 TOTAL CROSS SECTION 9746 1451 64 CASTHY /5/ CALCULATION WAS ADOPTED. 9746 1451 65 9746 1451 66 CASTHY CALCULATION 9746 1451 67 ------------------ 9746 1451 68 9746 1451 69 STATISTICAL MODEL CALCULATION WITH CASTHY CODE /5/ WAS 9746 1451 70 MADE CONSIDERING COMPETING PROCESSES OF FISSION, (N,2N) AND9746 1451 71 (N,3N). 9746 1451 72 9746 1451 73 SHERICAL OPTICAL POTENTIAL PARAMETERS /6/ 9746 1451 74 9746 1451 75 V = 45.036-0.3*EN (MEV) 9746 1451 76 WS= 4.115+0.4*EN (MEV) 9746 1451 77 WV= 0 , VSO = 7.5 (MEV) 9746 1451 78 R = RSO = 1.256 , RS = 1.260 (FM) 9746 1451 79 A = ASO = 0.626 , B = 0.555+0.0045*EN (FM) 9746 1451 80 9746 1451 81 9746 1451 82 THE LEVEL DENSITY PARAMETERS FOR GILBERT-CAMERON'S FORMULA 9746 1451 83 /7/ 9746 1451 84 ISOTOPE BK-247 BK-248 9746 1451 85 A(1/MEV) 28.1 27.8 9746 1451 86 SPIN-CUTOFF PARA. 30.47 30.39 9746 1451 87 PAIRING E(MEV) 0.39 0.0 9746 1451 88 TEMP. (MEV) 0.364 0.326 9746 1451 89 C(1/MEV) 2.9 10.8 9746 1451 90 EX(MEV) 7.97 1.85 9746 1451 91 9746 1451 92 THE LEVEL SCHEME TAKEN FROM REF. /8/. 9746 1451 93 NO. ENERGY(KEV) SPIN-PARITY 9746 1451 94 G.S. 0.0000 3/2 - 9746 1451 95 1. 29.900 5/2 - 9746 1451 96 2. 40.800 7/2 + 9746 1451 97 3. 71.600 7/2 - 9746 1451 98 4. 82.800 9/2 + 9746 1451 99 5. 125.50 9/2 - 9746 1451 100 6. 137.00 11/2 + 9746 1451 101 7. 196.00 13/2 + 9746 1451 102 8. 265.00 15/2 + 9746 1451 103 9. 334.90 5/2 + 9746 1451 104 10. 378.10 7/2 + 9746 1451 105 11. 447.80 5/2 - 9746 1451 106 12. 487.00 1/2 + 9746 1451 107 13. 489.40 7/2 - 9746 1451 108 14. 518.00 3/2 + 9746 1451 109 15. 541.00 9/2 - 9746 1451 110 16. 587.00 13/2 + 9746 1451 111 17. 704.00 1/2 - 9746 1451 112 18. 743.00 5/2 - 9746 1451 113 19. 815.00 7/2 - 9746 1451 114 20. 828.00 9/2 - 9746 1451 115 21. 904.00 9/2 - 9746 1451 116 CONTINUUM LEVELS ASSUMED ABOVE 983 KEV. 9746 1451 117 9746 1451 118 MT=2 ELASTIC SCATTRING 9746 1451 119 CALCULATED AS (TOTAL - SUM OF PARTIAL CROSS SECTIONS). 9746 1451 120 MT=4 TOTAL INELASTIC SCATTERING 9746 1451 121 SUM OF MT=51 TO 91. 9746 1451 122 MT=16,17,18 (N,2N), (N,3N), FISSION 9746 1451 123 STAPRE RESULTS CALCULATED BY KONSHIN /9/ WERE ADOPTED. 9746 1451 124 MT=51,53,55 (N,N') TO 1ST, 3RD AND 5TH LEVELS 9746 1451 125 CALCULATED WITH ECIS /10/ AND CASTHY /5/ CODES. 9746 1451 126 IN THE ECIS CALCULATION, CH.LAGRANGE'S DEFORMED OPTICAL 9746 1451 127 POTENTIAL PARAMETERS /11/ WERE USED. 9746 1451 128 V = 49.82 - 17*((N-Z)/A) - 0.3*EN (MEV) 9746 1451 129 WS = 5.52 - 9*((N-Z)/A)+ 0.4*EN (MEV), 0=