IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 5.81400E+4 1.38704E+2 0 0 1 15830 1451 1 0.0 0.0 0 0 0 05830 1451 2 0.0 0.0 0 0 50 35830 1451 3 58-Ce-140 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.5830 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 5830 1451 5 IDENTIFIER=INDL 5830 REV1 5830 1451 6 FORMAT= ENDF/B-5 5830 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 5830 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 5830 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 5830 1451 10 TEXT= 5830 1451 11 58-CE-140(N,2N)58-CE-139 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 5830 1451 12 58-CE-140(N,2N)58-CE-139M EN.REG.UP TO 20.MEV IN 100.KEV STEPS 5830 1451 13 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 5830 1451 14 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 5830 1451 15 OBNINSK,USSR). 5830 1451 16 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 5830 1451 17 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 5830 1451 18 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 5830 1451 19 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 5830 1451 20 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 5830 1451 21 KONSTANTY,32(1),PAGE 105,1979 5830 1451 22 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 5830 1451 23 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 5830 1451 24 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 5830 1451 25 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 5830 1451 26 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 5830 1451 27 YAD. KOSTANTY 3,(42),P.60,(1981) 5830 1451 28 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.5830 1451 29 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 5830 1451 30 REACTION | V.2,P.271,IAEA,VIENNA) 5830 1451 31 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 5830 1451 32 -------------|-------------|---------------|------------------ 5830 1451 33 58-CE-140(N,2N) | 1.32 | 1.14 | 1.57 5830 1451 34 58-CE-140(N,2N)M| 0.44 | 0.37 | 0.55 5830 1451 35 ***************** Program LINEAR (VERSION 2002-1) ***************5830 1451 36 For All Data Greater than 1.0000E-10 barns in Absolute Value 5830 1451 37 Data Linearized to Within an Accuracy of .100000000 per-cent 5830 1451 38 ***************** Program FIXUP (Version 2002-1) ****************5830 1451 39 Corrected ZA/AWR in All Sections-----------------------------Yes 5830 1451 40 Corrected Thresholds-----------------------------------------Yes 5830 1451 41 Extended Cross Sections to 20 MeV----------------------------No 5830 1451 42 Allow Cross Section Deletion---------------------------------No 5830 1451 43 Allow Cross Section Reconstruction---------------------------No 5830 1451 44 Make All Cross Sections Non-Negative-------------------------Yes 5830 1451 45 Delete Energies Not in Ascending Order-----------------------Yes 5830 1451 46 Deleted Duplicate Points-------------------------------------Yes 5830 1451 47 Check for Ascending MAT/MF/MT Order--------------------------Yes 5830 1451 48 Check for Legal MF/MT Numbers--------------------------------Yes 5830 1451 49 Allow Creation of Missing Sections---------------------------No 5830 1451 50 Allow Insertion of Energy Points-----------------------------No 5830 1451 51 Create Uniform Energy Grid-----------------------------------No 5830 1451 52 Delete Section if Cross Section =0 at All Energies-----------Yes 5830 1451 53 1 451 56 15830 1451 54 3 16 16 15830 1451 55 3 26 17 15830 1451 56 5830 1 0 57 5830 0 0 58 5.81400E+4 1.38704E+2 0 1 0 05830 3 16 59 2.93000E+2-9.20000E+6 0 0 1 395830 3 16 60 39 2 5830 3 16 61 9266328.30 0.0 9300000.00 0.0 9400000.00 .0200000005830 3 16 62 9600000.00 .180000000 9700000.00 .240000000 9800000.00 .3100000005830 3 16 63 9900000.00 .375000000 10000000.0 .435000000 10100000.0 .4891000005830 3 16 64 10200000.0 .542000000 10300000.0 .593600000 10400000.0 .6440000005830 3 16 65 10600000.0 .741000000 10800000.0 .833000000 11000000.0 .9200000005830 3 16 66 11200000.0 1.00000000 11400000.0 1.07600000 11600000.0 1.148000005830 3 16 67 11800000.0 1.21600000 12000000.0 1.28000000 12300000.0 1.367000005830 3 16 68 12600000.0 1.44700000 12900000.0 1.51800000 13200000.0 1.581000005830 3 16 69 13500000.0 1.63600000 13800000.0 1.68300000 14000000.0 1.710000005830 3 16 70 14500000.0 1.75600000 15000000.0 1.79000000 15500000.0 1.809000005830 3 16 71 16100000.0 1.82200000 16500000.0 1.82400000 17200000.0 1.812000005830 3 16 72 17600000.0 1.79300000 17900000.0 1.77000000 18000000.0 1.760000005830 3 16 73 18800000.0 1.64200000 19800000.0 1.47400000 20000000.0 1.440000005830 3 16 74 5830 3 0 75 5.81400E+4 1.38704E+2 0 1 0 05830 3 26 76 2.93000E+2-9.95000E+6 0 0 1 405830 3 26 77 40 2 5830 3 26 78 10021735.5 0.0 10070000.0 0.0 10100000.0 .0100000005830 3 26 79 10200000.0 .050000000 10400000.0 .110000000 10600000.0 .1800000005830 3 26 80 10700000.0 .220000000 10900000.0 .290000000 11000000.0 .3200000005830 3 26 81 11200000.0 .400000000 11300000.0 .437700000 11400000.0 .4740000005830 3 26 82 11500000.0 .508700000 11600000.0 .542000000 11700000.0 .5737000005830 3 26 83 11800000.0 .604000000 11900000.0 .632700000 12000000.0 .6600000005830 3 26 84 12200000.0 .706000000 12400000.0 .748000000 12600000.0 .7860000005830 3 26 85 12800000.0 .820000000 13000000.0 .850000000 13300000.0 .8833000005830 3 26 86 13600000.0 .911200000 13900000.0 .933700000 14200000.0 .9508000005830 3 26 87 14500000.0 .962500000 14800000.0 .968800000 15000000.0 .9700000005830 3 26 88 15300000.0 .966200000 15600000.0 .958000000 15900000.0 .9452000005830 3 26 89 16100000.0 .933300000 16500000.0 .903700000 16900000.0 .8693000005830 3 26 90 17300000.0 .831200000 17700000.0 .787200000 18000000.0 .7500000005830 3 26 91 20000000.0 .450000000 5830 3 26 92 5830 3 0 93 5830 0 0 94 0 0 0 95 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0