Retrieved by E4-util: 2010/02/01,11:45:41 1 0 0 0 9.824900+4 2.469350+2 1 1 59 09849 1451 1 0.000000+0 1.0000E+00 0 0 0 69849 1451 2 1.000000+0 2.0000E+07 0 0 10 09849 1451 3 0.000000+0 0.000000+0 0 0 208 819849 1451 4 98-Cf-249 IPPE EVAL-SEP06 Nikolaev M.N. 9849 1451 5 DIST-DEC06 9849 1451 6 ----RUSFOND Material 9849 9849 1451 7 -----Incident neutron data 9849 1451 8 ------ENDF-6 Format 9849 1451 9 9849 1451 10 RUSFOND DESCRIPTION 9849 1451 11 (See RUSFOND manual for details) 9849 1451 12 9849 1451 13 Data from JENDL-3.3 are adopted with the next exclusions 9849 1451 14 1. Delay neutron data MF=1, MT=455 are from JEFF-3.1 9849 1451 15 2. Delay neutron spectra are the same as for U-235, 9849 1451 16 but group yields taken from JEFF-3.1 9849 1451 17 3. MF8 MT454 and MT459 added using ENDF/B-VI data 9849 1451 18 JENDL-3.3 description 9849 1451 19 9849 1451 20 ************************************************************* 9849 1451 21 EVAL-JUL95 T.NAKAGAWA AND T.LIU 9849 1451 22 9849 1451 23 HISTORY 9849 1451 24 85-03 EVALUATION FOR JENDL-3 WAS MADE BY Y.KIKUCHI AND 9849 1451 25 T.NAKAGAWA (JAERI). DETAILS ARE GIVEN IN REF. /1/. 9849 1451 26 95-07 NEW EVALUATION WAS MADE BY T.NAKAGAWA AND T.LIU. 9849 1451 27 00-05 MODIFICATION AND COMPILATION WERE MADE BY T.NAKAGAWA 9849 1451 28 9849 1451 29 ***** Modified parts from JENDL-3.2 ******************* 9849 1451 30 MF=2 Scattering radius in the unresolved resonance 9849 1451 31 region. 9849 1451 32 ALL DATA OF MF'S = 3, 4 AND 5. 9849 1451 33 ******************************************************* 9849 1451 34 9849 1451 35 9849 1451 36 MF=1 GENERAL INFORMATION 9849 1451 37 MT=451 COMMENTS AND DICTIONARY 9849 1451 38 MT=452 NUMBER OF NEUTRONS PER FISSION 9849 1451 39 SUM OF MT'S = 455 AND 456. 9849 1451 40 MT=455 DELAYED NEUTRON DATA 9849 1451 41 SEMI-EMPIRICAL FORMULA BY TUTTLE /2/. 9849 1451 42 MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION 9849 1451 43 SEMI-EMPIRICAL FORMULA BY HOWERTON /3/. 9849 1451 44 9849 1451 45 MF=2,MT=151 RESONANCE PARAMETERS (TAKEN FROM JENDL-3.2) 9849 1451 46 RESOLVED RESONANCES FOR MLBW FORMULA : 1.0E-5 EV TO 70 EV 9849 1451 47 RESONANCE ENERGIES, NEUTRON AND FISSION WIDTHS WERE TAKEN 9849 1451 48 FROM THE EXPERIMENTAL DATA OF BENJAMIN+ /4/. THE RADIATIVE 9849 1451 49 WIDTH WAS ASSUMED TO BE 0.04 EV ACCORDING TO DABBS+ /5/. 9849 1451 50 A NEGATIVE RESONANCE WAS ADDED SO AS TO REPRODUCE THE THERMAL 9849 1451 51 CROSS SECTIONS. NO BACKGROUND CORRECTION WAS APPLIED. 9849 1451 52 9849 1451 53 UNRESOLVED RESONANCES : 70 EV - 30 KEV 9849 1451 54 OBTAINED FROM OPTICAL MODEL CALCULATION: 9849 1451 55 S1=3.15E-4, S2=0.83E-4. 9849 1451 56 ESTIMATED FROM RESOLVED RESONANCES: 9849 1451 57 DOBS=1.16 EV, GAM-G=40 MILLI-EV ,S0=1.06E-4 9849 1451 58 FISSION WIDTHS WERE ESTIMATED FROM THE CHANNEL THEORY OF 9849 1451 59 FISSION /6/. S0, S1 AND S2 VALUES WERE ADJUSTED SO AS TO 9849 1451 60 REPRODUCE THE FISSION CROSS SECTION MEASURED BY DABBS+ /5/. 9849 1451 61 Scattering radius of 8.85 fm was determined so as to give the 9849 1451 62 same ealstic scattering cross section above 30 keV. 9849 1451 63 9849 1451 64 CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS 9849 1451 65 2200 M/S VALUE RES. INT. 9849 1451 66 TOTAL 2176.7 B - 9849 1451 67 ELASTIC 6.22 B - 9849 1451 68 FISSION 1666 B 2220 B 9849 1451 69 CAPTURE 504.5 B 695 B 9849 1451 70 9849 1451 71 MF=3 NEUTRON CROSS SECTIONS 9849 1451 72 MT=1 TOTAL CROSS SECTION 9849 1451 73 CALCULATED WITH CASTHY CODE /7/ BASED ON THE SHERICAL 9849 1451 74 OPTICAL MODEL. THE OPTICAL POTENTIAL OF REF./8/ WERE 9849 1451 75 USED. 9849 1451 76 9849 1451 77 V = 45.036-0.3*EN (MEV) 9849 1451 78 WS= 4.115+0.4*EN (MEV) 9849 1451 79 WV= 0 , VSO = 7.5 (MEV) 9849 1451 80 R = RSO = 1.256 , RS = 1.260 (FM) 9849 1451 81 A = ASO = 0.626 , B = 0.555+0.0045*EN (FM) 9849 1451 82 9849 1451 83 COMPETING PROCESSES OF THE FISSION, (N,2N) AND (N,3N) WERE 9849 1451 84 TAKEN INTO ACCOUNT. THE FOLLOWING LEVEL DENSITY PARAMETERS 9849 1451 85 OF GILBERT-CAMERON'S FORMULA /9/ WERE USED. 9849 1451 86 9849 1451 87 ISOTOPE CF-249 CF-250 9849 1451 88 A(1/MEV) 29.4 31.2 9849 1451 89 SPIN-CUTOFF FACT 31.33 32.36 9849 1451 90 PAIRING E(MEV) 0.77 1.673 9849 1451 91 TEMP.(MEV) 0.3693 0.4025 9849 1451 92 C(1/MEV) 4.644 2.111 9849 1451 93 EX(MEV) 3.562 5.423 9849 1451 94 9849 1451 95 THE LEVEL SCHEME TAKEN FROM REF. /10/. 9849 1451 96 NO. ENERGY(KEV) SPIN-PARITY 9849 1451 97 G.S. 0 9/2 - 9849 1451 98 1. 62.49 11/2 - 9849 1451 99 2. 136.2 13/2 - 9849 1451 100 3. 144.96 5/2 + 9849 1451 101 4. 187.94 7/2 + 9849 1451 102 5. 220.0 15/2 - 9849 1451 103 6. 243.07 9/2 + 9849 1451 104 7. 315.0 17/2 - 9849 1451 105 8. 315.1 11/2 + 9849 1451 106 9. 379.52 7/2 + 9849 1451 107 10. 384.0 13/2 + 9849 1451 108 11. 416.8 1/2 + 9849 1451 109 12. 425.0 19/2 - 9849 1451 110 13. 437.56 9/2 + 9849 1451 111 14. 440.0 3/2 + 9849 1451 112 15. 442.98 7/2 + 9849 1451 113 16. 460.0 5/2 + 9849 1451 114 17. 500.7 9/2 + 9849 1451 115 18. 550.0 1/2 + 9849 1451 116 19. 606.0 5/2 + 9849 1451 117 20. 668.0 13/2 - 9849 1451 118 21. 751.0 15/2 - 9849 1451 119 22. 813.20 5/2 - 9849 1451 120 23. 852.19 7/2 - 9849 1451 121 24. 902.5 9/2 - 9849 1451 122 25. 920.0 11/2 + 9849 1451 123 26. 962.0 11/2 - 9849 1451 124 27. 992.0 13/2 + 9849 1451 125 28. 1008.0 9/2 + 9849 1451 126 CONTINUUM LEVELS ASSUMED ABOVE 1031. KEV. 9849 1451 127 9849 1451 128 MT= 2 ELASTIC SCATTERING 9849 1451 129 CALCULATED AS TOTAL - PARTIAL CROSS SECTIONS. 9849 1451 130 9849 1451 131 MT= 4 TOTAL INELASTIC SCATTERING 9849 1451 132 SUM OF MT=51 to 78 AND 91. 9849 1451 133 9849 1451 134 MT=16,17 (N,2N), (N,3N) CROSS SECTIONS 9849 1451 135 STAPRE RESULTS CALCULATED BY KONSHIN /11/ were adopted. 9849 1451 136 9849 1451 137 MT=18 FISSION CROSS SECTION 9849 1451 138 DATA WERE TAKEN FROM JENDL-3.2 WHICH WAS EVALUATED ON THE 9849 1451 139 BASIS OF THE MEASURED DATA BY DABBS+ /5/, SILBERT/12/ 9849 1451 140 AND KUPRIYANOV+ /13/. 9849 1451 141 9849 1451 142 MT=51, 52, 55 9849 1451 143 CALCULATED WITH ECIS /14/ AND CASTHY /7/ CODES. 9849 1451 144 LAGRANGE'S DEFORMED OPTICAL POTENTIAL PARAMETERS /15/ 9849 1451 145 WERE USED. 9849 1451 146 V = 49.82 - 17*((N-Z)/A) - 0.3*EN (MEV) 9849 1451 147 WS = 5.52 - 9*((N-Z)/A)+ 0.4*EN (MEV) EN=< 10 MEV 9849 1451 148 = 9.52 - 9*((N-Z)/A) (MEV) 10 =