IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 8.12030E+4 2.01229E+2 0 0 1 28110 1451 1 0.0 0.0 0 0 0 08110 1451 2 0.0 0.0 0 0 67 38110 1451 3 81-Tl-203 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.8110 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 8110 1451 5 IDENTIFIER=INDL 8110 REV2 8110 1451 6 FORMAT= ENDF/B-5 8110 1451 7 =============================================================== 8110 1451 8 ======================== For MF = 16 ======================== 8110 1451 9 8110 1451 10 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 8110 1451 11 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO ENDF/B-5 8110 1451 12 FORMAT.APPROVED BY AUTHOR.SUPERSEDES BOSPOR-78=8110 REV1 VP. 8110 1451 13 TEXT= 8110 1451 14 81-TL-203(N,2N)81-TL-202 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 8110 1451 15 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 8110 1451 16 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 8110 1451 17 OBNINSK,USSR). 8110 1451 18 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 8110 1451 19 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 8110 1451 20 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 8110 1451 21 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 8110 1451 22 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 8110 1451 23 KONSTANTY,32(1),PAGE 105,1979 8110 1451 24 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 8110 1451 25 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 8110 1451 26 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 8110 1451 27 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 8110 1451 28 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 8110 1451 29 YAD. KOSTANTY 3,(42),P.60,(1981) 8110 1451 30 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.8110 1451 31 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 8110 1451 32 REACTION | V.2,P.271,IAEA,VIENNA) 8110 1451 33 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 8110 1451 34 -------------|-------------|---------------|------------------ 8110 1451 35 81-TL-203(N,2N) | 3.08 | 2.71 | 3.49 8110 1451 36 =============================================================== 8110 1451 37 ======================== For MF = 103 ======================== 8110 1451 38 0.81203E 05 0.2012E 03 0 0 1 18110 1451 39 0.0 0.0 0 0 0 08110 1451 40 0.0 0.0 0 0 9 28110 1451 41 81-Tl-203 1USALRL EVAL- 82 8110 1451 42 8110 1451 43 IDENTIFIER=ENDL 8135 8110 1451 44 FORMAT= ENDF/B-5 8110 1451 45 HISTORY= 840315 DATA WERE CONVERTED IN ENDF/B-5 FORMAT BY NDS 8110 1451 46 8110 1451 47 TEXT= 8110 1451 48 THIS EVALUATED CROSS-SECTION WAS TAKEN FROM LIVERMORE ACTIVATION 8110 1451 49 LIBRARY 8110 1451 50 8110 1451 51 =============================================================== 8110 1451 52 ***************** Program LINEAR (VERSION 2002-1) ***************8110 1451 53 For All Data Greater than 1.0000E-10 barns in Absolute Value 8110 1451 54 Data Linearized to Within an Accuracy of .100000000 per-cent 8110 1451 55 ***************** Program FIXUP (Version 2002-1) ****************8110 1451 56 Corrected ZA/AWR in All Sections-----------------------------Yes 8110 1451 57 Corrected Thresholds-----------------------------------------Yes 8110 1451 58 Extended Cross Sections to 20 MeV----------------------------No 8110 1451 59 Allow Cross Section Deletion---------------------------------No 8110 1451 60 Allow Cross Section Reconstruction---------------------------No 8110 1451 61 Make All Cross Sections Non-Negative-------------------------Yes 8110 1451 62 Delete Energies Not in Ascending Order-----------------------Yes 8110 1451 63 Deleted Duplicate Points-------------------------------------Yes 8110 1451 64 Check for Ascending MAT/MF/MT Order--------------------------Yes 8110 1451 65 Check for Legal MF/MT Numbers--------------------------------Yes 8110 1451 66 Allow Creation of Missing Sections---------------------------No 8110 1451 67 Allow Insertion of Energy Points-----------------------------No 8110 1451 68 Create Uniform Energy Grid-----------------------------------No 8110 1451 69 Delete Section if Cross Section =0 at All Energies-----------Yes 8110 1451 70 1 451 73 18110 1451 71 3 16 19 28110 1451 72 3 103 10 18110 1451 73 8110 1 0 74 8110 0 0 75 8.12030E+4 2.01229E+2 0 1 0 08110 3 16 76 2.93000E+2-7.72000E+6 0 0 1 488110 3 16 77 48 2 8110 3 16 78 7758364.25 0.0 7900000.00 0.0 8000000.00 .0040000008110 3 16 79 8100000.00 .026950000 8200000.00 .052510000 8300000.00 .0806800008110 3 16 80 8400000.00 .111400000 8500000.00 .144800000 8600000.00 .1808000008110 3 16 81 8700000.00 .219400000 8800000.00 .260600000 8900000.00 .3044000008110 3 16 82 9000000.00 .350800000 9100000.00 .417200000 9200000.00 .4824000008110 3 16 83 9300000.00 .546300000 9500000.00 .670300000 9700000.00 .7892000008110 3 16 84 9900000.00 .903100000 10200000.0 1.07000000 10400000.0 1.174000008110 3 16 85 10600000.0 1.27000000 10800000.0 1.35900000 11000000.0 1.439000008110 3 16 86 11300000.0 1.53700000 11700000.0 1.65200000 12000000.0 1.727000008110 3 16 87 12300000.0 1.79000000 12700000.0 1.86300000 13000000.0 1.910000008110 3 16 88 13500000.0 1.96900000 14300000.0 2.04800000 14700000.0 2.074000008110 3 16 89 15000000.0 2.08000000 15400000.0 2.06700000 15800000.0 2.041000008110 3 16 90 16200000.0 2.00500000 16600000.0 1.95600000 16900000.0 1.909000008110 3 16 91 17200000.0 1.85300000 17600000.0 1.76800000 18000000.0 1.670000008110 3 16 92 18700000.0 1.46100000 19000000.0 1.37500000 19300000.0 1.285000008110 3 16 93 19600000.0 1.20100000 19900000.0 1.12400000 20000000.0 1.100000008110 3 16 94 8110 3 0 95 8.12030E+4 2.01229E+2 0 0 0 08110 3103 96 2.93000E+2 2.90000E+5 0 0 1 208110 3103 97 20 2 8110 3103 98 10000000.0 0.0 10300000.0 .000124100 10600000.0 .0004749008110 3103 99 10900000.0 .000993800 11500000.0 .002216000 11800000.0 .0027740008110 3103 100 12100000.0 .003234000 12400000.0 .003584000 12700000.0 .0038300008110 3103 101 13000000.0 .003991000 13600000.0 .004144000 15400000.0 .0042000008110 3103 102 16000000.0 .004152000 16300000.0 .004035000 16900000.0 .0036450008110 3103 103 18100000.0 .002739000 18700000.0 .002431000 19300000.0 .0022490008110 3103 104 19900000.0 .002158000 20000000.0 .002158000 8110 3103 105 8110 3 0 106 8110 0 0 107 0 0 0 108 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0