IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 5.81420E+4 1.40690E+2 0 0 1 15840 1451 1 0.0 0.0 0 0 0 05840 1451 2 0.0 0.0 0 0 48 25840 1451 3 58-Ce-142 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.5840 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 5840 1451 5 IDENTIFIER=INDL 5840 REV1 5840 1451 6 FORMAT= ENDF/B-5 5840 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 5840 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 5840 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 5840 1451 10 TEXT= 5840 1451 11 58-CE-142(N,2N)58-CE-141 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 5840 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 5840 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 5840 1451 14 OBNINSK,USSR). 5840 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 5840 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 5840 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 5840 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 5840 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 5840 1451 20 KONSTANTY,32(1),PAGE 105,1979 5840 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 5840 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 5840 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 5840 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 5840 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 5840 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 5840 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.5840 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 5840 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 5840 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 5840 1451 31 -------------|-------------|---------------|------------------ 5840 1451 32 58-CE-142(N,2N) | 7.3 | 6.6 | 7.8 5840 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************5840 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 5840 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 5840 1451 36 ***************** Program FIXUP (Version 2002-1) ****************5840 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 5840 1451 38 Corrected Thresholds-----------------------------------------Yes 5840 1451 39 Extended Cross Sections to 20 MeV----------------------------No 5840 1451 40 Allow Cross Section Deletion---------------------------------No 5840 1451 41 Allow Cross Section Reconstruction---------------------------No 5840 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 5840 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 5840 1451 44 Deleted Duplicate Points-------------------------------------Yes 5840 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 5840 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 5840 1451 47 Allow Creation of Missing Sections---------------------------No 5840 1451 48 Allow Insertion of Energy Points-----------------------------No 5840 1451 49 Create Uniform Energy Grid-----------------------------------No 5840 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 5840 1451 51 1 451 53 15840 1451 52 3 16 17 15840 1451 53 5840 1 0 54 5840 0 0 55 5.81420E+4 1.40690E+2 0 1 0 05840 3 16 56 2.93000E+2-7.16000E+6 0 0 1 415840 3 16 57 41 2 5840 3 16 58 7210892.03 0.0 7220000.00 .100000000 7300000.00 .1500000005840 3 16 59 8000000.00 .500000000 8100000.00 .556700000 8200000.00 .6120000005840 3 16 60 8300000.00 .665700000 8400000.00 .718000000 8600000.00 .8180000005840 3 16 61 8800000.00 .912000000 9000000.00 1.00000000 9200000.00 1.083000005840 3 16 62 9400000.00 1.15900000 9600000.00 1.22900000 9800000.00 1.293000005840 3 16 63 10000000.0 1.35000000 10300000.0 1.41600000 10600000.0 1.475000005840 3 16 64 11000000.0 1.54000000 11800000.0 1.62200000 12500000.0 1.685000005840 3 16 65 13200000.0 1.73400000 13600000.0 1.75200000 13900000.0 1.759000005840 3 16 66 14300000.0 1.76400000 14600000.0 1.75600000 14800000.0 1.746000005840 3 16 67 15000000.0 1.73000000 15300000.0 1.69200000 15600000.0 1.648000005840 3 16 68 15900000.0 1.59800000 16100000.0 1.55900000 16900000.0 1.383000005840 3 16 69 17200000.0 1.31000000 17600000.0 1.21200000 18000000.0 1.120000005840 3 16 70 19000000.0 .910000000 19300000.0 .840700000 19600000.0 .7768000005840 3 16 71 19900000.0 .718300000 20000000.0 .700000000 5840 3 16 72 5840 3 0 73 5840 0 0 74 0 0 0 75 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0