IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 8.12050E+4 2.03214E+2 0 0 1 18140 1451 1 0.0 0.0 0 0 0 08140 1451 2 0.0 0.0 0 0 67 38140 1451 3 81-Tl-205 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.8140 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 8140 1451 5 IDENTIFIER=INDL 8140 REV1 8140 1451 6 FORMAT= ENDF/B-5 8140 1451 7 =============================================================== 8140 1451 8 ========================= For MF = 16 ======================= 8140 1451 9 8140 1451 10 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 8140 1451 11 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 8140 1451 12 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 8140 1451 13 TEXT= 8140 1451 14 81-TL-205(N,2N)81-TL-204 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 8140 1451 15 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 8140 1451 16 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 8140 1451 17 OBNINSK,USSR). 8140 1451 18 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 8140 1451 19 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 8140 1451 20 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 8140 1451 21 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 8140 1451 22 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 8140 1451 23 KONSTANTY,32(1),PAGE 105,1979 8140 1451 24 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 8140 1451 25 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 8140 1451 26 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 8140 1451 27 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 8140 1451 28 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 8140 1451 29 YAD. KOSTANTY 3,(42),P.60,(1981) 8140 1451 30 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.8140 1451 31 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 8140 1451 32 REACTION | V.2,P.271,IAEA,VIENNA) 8140 1451 33 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 8140 1451 34 -------------|-------------|---------------|------------------ 8140 1451 35 81-TL-205(N,2N) | 3.78 | 3.34 | 4.24 8140 1451 36 =============================================================== 8140 1451 37 ========================= For MF = 103 ======================= 8140 1451 38 0.81205E 05 0.2032E 03 0 0 1 18140 1451 39 0.0 0.0 0 0 0 08140 1451 40 0.0 0.0 0 0 9 28140 1451 41 81-Tl-205 1USALRL EVAL- 82 8140 1451 42 8140 1451 43 IDENTIFIER=ENDL 8136 8140 1451 44 FORMAT= ENDF/B-5 8140 1451 45 HISTORY= 840315 DATA WERE CONVERTED IN ENDF/B-5 FORMAT BY NDS 8140 1451 46 8140 1451 47 TEXT= 8140 1451 48 THIS EVALUATED CROSS-SECTION WAS TAKEN FROM LIVERMORE ACTIVATION 8140 1451 49 LIBRARY 8140 1451 50 8140 1451 51 =============================================================== 8140 1451 52 ***************** Program LINEAR (VERSION 2002-1) ***************8140 1451 53 For All Data Greater than 1.0000E-10 barns in Absolute Value 8140 1451 54 Data Linearized to Within an Accuracy of .100000000 per-cent 8140 1451 55 ***************** Program FIXUP (Version 2002-1) ****************8140 1451 56 Corrected ZA/AWR in All Sections-----------------------------Yes 8140 1451 57 Corrected Thresholds-----------------------------------------Yes 8140 1451 58 Extended Cross Sections to 20 MeV----------------------------No 8140 1451 59 Allow Cross Section Deletion---------------------------------No 8140 1451 60 Allow Cross Section Reconstruction---------------------------No 8140 1451 61 Make All Cross Sections Non-Negative-------------------------Yes 8140 1451 62 Delete Energies Not in Ascending Order-----------------------Yes 8140 1451 63 Deleted Duplicate Points-------------------------------------Yes 8140 1451 64 Check for Ascending MAT/MF/MT Order--------------------------Yes 8140 1451 65 Check for Legal MF/MT Numbers--------------------------------Yes 8140 1451 66 Allow Creation of Missing Sections---------------------------No 8140 1451 67 Allow Insertion of Energy Points-----------------------------No 8140 1451 68 Create Uniform Energy Grid-----------------------------------No 8140 1451 69 Delete Section if Cross Section =0 at All Energies-----------Yes 8140 1451 70 1 451 73 18140 1451 71 3 16 18 18140 1451 72 3 103 10 18140 1451 73 8140 1 0 74 8140 0 0 75 8.12050E+4 2.03214E+2 0 1 0 08140 3 16 76 2.93000E+2-7.54000E+6 0 0 1 448140 3 16 77 44 2 8140 3 16 78 7577103.74 0.0 8100000.00 0.0 8200000.00 .0200000008140 3 16 79 8400000.00 .170000000 8500000.00 .230000000 8800000.00 .4400000008140 3 16 80 9000000.00 .570000000 9100000.00 .640900000 9200000.00 .7096000008140 3 16 81 9300000.00 .776100000 9400000.00 .840400000 9500000.00 .9025000008140 3 16 82 9600000.00 .962400000 9800000.00 1.07600000 10000000.0 1.180000008140 3 16 83 10200000.0 1.27000000 10400000.0 1.35400000 10600000.0 1.432000008140 3 16 84 10800000.0 1.50400000 11000000.0 1.57000000 11200000.0 1.627000008140 3 16 85 11500000.0 1.70400000 11800000.0 1.77100000 12000000.0 1.810000008140 3 16 86 12300000.0 1.85600000 12600000.0 1.89600000 12900000.0 1.930000008140 3 16 87 13200000.0 1.95700000 13700000.0 1.98800000 14000000.0 2.000000008140 3 16 88 14600000.0 2.00600000 15100000.0 1.99700000 15600000.0 1.975000008140 3 16 89 16100000.0 1.94300000 16600000.0 1.90100000 17300000.0 1.829000008140 3 16 90 17600000.0 1.79200000 18000000.0 1.73000000 18300000.0 1.679000008140 3 16 91 18600000.0 1.61700000 18900000.0 1.54600000 19000000.0 1.520000008140 3 16 92 19600000.0 1.32600000 20000000.0 1.20000000 8140 3 16 93 8140 3 0 94 8.12050E+4 2.03214E+2 0 0 0 08140 3103 95 2.93000E+2-7.55000E+5 0 0 1 198140 3103 96 19 2 8140 3103 97 758715.295 0.0 11030000.0 0.0 11330000.0 5.61500E-58140 3103 98 11630000.0 .000214800 11930000.0 .000449600 12530000.0 .0010020008140 3103 99 12830000.0 .001255000 13130000.0 .001463000 13430000.0 .0016210008140 3103 100 13730000.0 .001733000 14330000.0 .001850000 14930000.0 .0018880008140 3103 101 16130000.0 .001900000 16730000.0 .001875000 17030000.0 .0018200008140 3103 102 18830000.0 .001232000 19130000.0 .001156000 19730000.0 .0010490008140 3103 103 20000000.0 .001049000 8140 3103 104 8140 3 0 105 8140 0 0 106 0 0 0 107 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0