JENDL-3.3 Bk-247 0 0 0 0 9.724700+4 2.449480+2 1 1 0 19746 1451 1 0.000000+0 0.000000+0 0 0 0 69746 1451 2 1.000000+0 2.000000+7 3 0 10 39746 1451 3 0.000000+0 0.000000+0 0 0 172 649746 1451 4 97-BK-247 JAERI EVAL-JUN95 T.NAKAGAWA AND T.LIU 9746 1451 5 JAERI-RESEARCH 97-056 DIST-MAR02 20000911 9746 1451 6 ----JENDL-3.3 MATERIAL 9746 9746 1451 7 -----INCIDENT NEUTRON DATA 9746 1451 8 ------ENDF-6 FORMAT 9746 1451 9 9746 1451 10 HISTORY 9746 1451 11 95-06 NEW EVALUATION FOR JENDL ACTINIDE FILE WAS MADE BY 9746 1451 12 T.NAKAGAWA AND T.LIU /1/. 9746 1451 13 99-12 RECOMPILED BY T.NAKAGAWA. 9746 1451 14 THE FOLLOWING QUANTITIES ARE RE-EVALUATED AFTER JAERI- 9746 1451 15 RESEARCH 97-056: 9746 1451 16 MF=3 MT=102 DIRECT/SEMI-DIRECT MODIFIED. 9746 1451 17 MF=4 MT= 2 BELOW 500 KEV, REPLACED WITH CASTHY CALC. 9746 1451 18 MF=5 MT=16, 17, 18, 91 9746 1451 19 9746 1451 20 9746 1451 21 MF=1 GENERAL INFORMATION 9746 1451 22 MT=451 COMMENTS AND DICTIONARY 9746 1451 23 MT=452 NUMBER OF NEUTRONS PER FISSION 9746 1451 24 SUM OF MT'S =455 AND 456. 9746 1451 25 MT=455 DELAYED NEUTRON DATA 9746 1451 26 SEMI-EMPIRICAL FORMULA BY TUTTLE /2/. 9746 1451 27 MT=456 PROMPT NEUTRON DATA 9746 1451 28 SEMI-EMPIRICAL FORMULA BY HOWERTON /3/. 9746 1451 29 9746 1451 30 MF=2,MT=151 RESONANCE PARAMETERS 9746 1451 31 RESOLVED RESONANCE REGION (SLBW) : 1.0E-5 TO 150 EV 9746 1451 32 HYPOTHETICAL RESONANCE LEVELS WERE GIVE. THEIR PARAMETERS 9746 1451 33 WERE DETERMINED SO AS TO REPRODUCE THERMAL CROSS SECTIONS. 9746 1451 34 ASSUMED DATA WERE: 9746 1451 35 S-WAVE NEUTRON STRENGTH FUNCTION = 1.0E-4 9746 1451 36 AVERAGE LEVEL SPACING = 2.01 EV (FROM LEVEL DENSITY 9746 1451 37 PARAMETERS) 9746 1451 38 RADIATIVE WIDTH = 0.026 EV /4/ 9746 1451 39 FISSION WIDTH = 0.013 EV (FROM THE RATIO OF CAPTURE 9746 1451 40 AND FISSION CROSS SECTIONS 9746 1451 41 AT THE THERMAL ENERGY) 9746 1451 42 SCATTERING RADIUS = 9.27 FM (CALCULATED WITH OPTICAL 9746 1451 43 MODEL) 9746 1451 44 9746 1451 45 NO UNRESOLVED RESONANCE PARAMETERS WERE GIVEN. 9746 1451 46 9746 1451 47 CALCULATED 2200 M/S CROSS SECTIONS AND RES. INTEGRAL 9746 1451 48 2200 M/S RES. INTEGRAL 9746 1451 49 TOTAL 288.2 B 9746 1451 50 ELASTIC 12.33 B 9746 1451 51 FISSION 91.96 B 453 B 9746 1451 52 CAPTURE 183.9 B 896 B 9746 1451 53 9746 1451 54 MF=3 NEUTRON CROSS SECTIONS 9746 1451 55 CROSS SECTIONS IN THE ENERGY RANGE BELOE 150 EV WERE 9746 1451 56 REPRESENTED WITH RESONANCE PARAMETERS. 9746 1451 57 9746 1451 58 MT=1 TOTAL CROSS SECTION 9746 1451 59 CASTHY /5/ CALCULATION WAS ADOPTED. 9746 1451 60 9746 1451 61 CASTHY CALCULATION 9746 1451 62 ------------------ 9746 1451 63 9746 1451 64 STATISTICAL MODEL CALCULATION WITH CASTHY CODE /5/ WAS 9746 1451 65 MADE CONSIDERING COMPETING PROCESSES OF FISSION, (N,2N) AND9746 1451 66 (N,3N). 9746 1451 67 9746 1451 68 SHERICAL OPTICAL POTENTIAL PARAMETERS /6/ 9746 1451 69 9746 1451 70 V = 45.036-0.3*EN (MEV) 9746 1451 71 WS= 4.115+0.4*EN (MEV) 9746 1451 72 WV= 0 , VSO = 7.5 (MEV) 9746 1451 73 R = RSO = 1.256 , RS = 1.260 (FM) 9746 1451 74 A = ASO = 0.626 , B = 0.555+0.0045*EN (FM) 9746 1451 75 9746 1451 76 9746 1451 77 THE LEVEL DENSITY PARAMETERS FOR GILBERT-CAMERON'S FORMULA 9746 1451 78 /7/ 9746 1451 79 ISOTOPE BK-247 BK-248 9746 1451 80 A(1/MEV) 28.1 27.8 9746 1451 81 SPIN-CUTOFF PARA. 30.47 30.39 9746 1451 82 PAIRING E(MEV) 0.39 0.0 9746 1451 83 TEMP. (MEV) 0.364 0.326 9746 1451 84 C(1/MEV) 2.9 10.8 9746 1451 85 EX(MEV) 7.97 1.85 9746 1451 86 9746 1451 87 THE LEVEL SCHEME TAKEN FROM REF. /8/. 9746 1451 88 NO. ENERGY(KEV) SPIN-PARITY 9746 1451 89 G.S. 0.0000 3/2 - 9746 1451 90 1. 29.900 5/2 - 9746 1451 91 2. 40.800 7/2 + 9746 1451 92 3. 71.600 7/2 - 9746 1451 93 4. 82.800 9/2 + 9746 1451 94 5. 125.50 9/2 - 9746 1451 95 6. 137.00 11/2 + 9746 1451 96 7. 196.00 13/2 + 9746 1451 97 8. 265.00 15/2 + 9746 1451 98 9. 334.90 5/2 + 9746 1451 99 10. 378.10 7/2 + 9746 1451 100 11. 447.80 5/2 - 9746 1451 101 12. 487.00 1/2 + 9746 1451 102 13. 489.40 7/2 - 9746 1451 103 14. 518.00 3/2 + 9746 1451 104 15. 541.00 9/2 - 9746 1451 105 16. 587.00 13/2 + 9746 1451 106 17. 704.00 1/2 - 9746 1451 107 18. 743.00 5/2 - 9746 1451 108 19. 815.00 7/2 - 9746 1451 109 20. 828.00 9/2 - 9746 1451 110 21. 904.00 9/2 - 9746 1451 111 CONTINUUM LEVELS ASSUMED ABOVE 983 KEV. 9746 1451 112 9746 1451 113 MT=2 ELASTIC SCATTRING 9746 1451 114 CALCULATED AS (TOTAL - SUM OF PARTIAL CROSS SECTIONS). 9746 1451 115 MT=4 TOTAL INELASTIC SCATTERING 9746 1451 116 SUM OF MT=51 TO 91. 9746 1451 117 MT=16,17,18 (N,2N), (N,3N), FISSION 9746 1451 118 STAPRE RESULTS CALCULATED BY KONSHIN /9/ WERE ADOPTED. 9746 1451 119 MT=51,53,55 (N,N') TO 1ST, 3RD AND 5TH LEVELS 9746 1451 120 CALCULATED WITH ECIS /10/ AND CASTHY /5/ CODES. 9746 1451 121 IN THE ECIS CALCULATION, CH.LAGRANGE'S DEFORMED OPTICAL 9746 1451 122 POTENTIAL PARAMETERS /11/ WERE USED. 9746 1451 123 V = 49.82 - 17*((N-Z)/A) - 0.3*EN (MEV) 9746 1451 124 WS = 5.52 - 9*((N-Z)/A)+ 0.4*EN (MEV), 0=