IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 8.22040E+4 2.02221E+2 0 0 1 18230 1451 1 0.0 0.0 0 0 0 08230 1451 2 0.0 0.0 0 0 68 38230 1451 3 82-Pb-204 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.8230 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 8230 1451 5 IDENTIFIER=INDL 8230 REV1 8230 1451 6 FORMAT= ENDF/B-5 8230 1451 7 =============================================================== 8230 1451 8 ======================== For MF = 16 ======================== 8230 1451 9 8230 1451 10 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 8230 1451 11 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 8230 1451 12 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 8230 1451 13 TEXT= 8230 1451 14 82-PB-204(N,2N)82-PB-204 EN.REG.UP TO 20.MEV IN STEPS OF 100.KEV 8230 1451 15 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 8230 1451 16 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 8230 1451 17 OBNINSK,USSR). 8230 1451 18 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 8230 1451 19 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 8230 1451 20 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 8230 1451 21 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 8230 1451 22 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 8230 1451 23 KONSTANTY,32(1),PAGE 105,1979 8230 1451 24 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 8230 1451 25 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 8230 1451 26 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 8230 1451 27 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 8230 1451 28 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 8230 1451 29 YAD. KOSTANTY 3,(42),P.60,(1981) 8230 1451 30 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.8230 1451 31 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 8230 1451 32 REACTION | V.2,P.271,IAEA,VIENNA) 8230 1451 33 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 8230 1451 34 -------------|-------------|---------------|------------------ 8230 1451 35 82-PB-204(N,2N)| 2.06 | 1.79 | 2.41 8230 1451 36 8230 1451 37 =============================================================== 8230 1451 38 ======================== For MF = 103 ======================== 8230 1451 39 0.82204E 05 0.2022E 03 0 0 1 18230 1451 40 0.0 0.0 0 0 0 08230 1451 41 0.0 0.0 0 0 9 28230 1451 42 82-Pb-204 1USALRL EVAL- 81 8230 1451 43 8230 1451 44 IDENTIFIER=ENDL 8235 8230 1451 45 FORMAT= ENDF/B-5 8230 1451 46 HISTORY= 840315 DATA WERE CONVERTED IN ENDF/B-5 FORMAT BY NDS 8230 1451 47 8230 1451 48 TEXT= 8230 1451 49 THIS EVALUATED CROSS-SECTION WAS TAKEN FROM LIVERMORE ACTIVATION 8230 1451 50 LIBRARY 8230 1451 51 8230 1451 52 =============================================================== 8230 1451 53 ***************** Program LINEAR (VERSION 2002-1) ***************8230 1451 54 For All Data Greater than 1.0000E-10 barns in Absolute Value 8230 1451 55 Data Linearized to Within an Accuracy of .100000000 per-cent 8230 1451 56 ***************** Program FIXUP (Version 2002-1) ****************8230 1451 57 Corrected ZA/AWR in All Sections-----------------------------Yes 8230 1451 58 Corrected Thresholds-----------------------------------------Yes 8230 1451 59 Extended Cross Sections to 20 MeV----------------------------No 8230 1451 60 Allow Cross Section Deletion---------------------------------No 8230 1451 61 Allow Cross Section Reconstruction---------------------------No 8230 1451 62 Make All Cross Sections Non-Negative-------------------------Yes 8230 1451 63 Delete Energies Not in Ascending Order-----------------------Yes 8230 1451 64 Deleted Duplicate Points-------------------------------------Yes 8230 1451 65 Check for Ascending MAT/MF/MT Order--------------------------Yes 8230 1451 66 Check for Legal MF/MT Numbers--------------------------------Yes 8230 1451 67 Allow Creation of Missing Sections---------------------------No 8230 1451 68 Allow Insertion of Energy Points-----------------------------No 8230 1451 69 Create Uniform Energy Grid-----------------------------------No 8230 1451 70 Delete Section if Cross Section =0 at All Energies-----------Yes 8230 1451 71 1 451 74 18230 1451 72 3 16 18 18230 1451 73 3 103 9 18230 1451 74 8230 1 0 75 8230 0 0 76 8.22040E+4 2.02221E+2 0 0 0 08230 3 16 77 2.93000E+2-8.40000E+6 0 0 1 438230 3 16 78 43 2 8230 3 16 79 8441538.71 0.0 8900000.00 0.0 9000000.00 .0480000008230 3 16 80 9100000.00 .116000000 9200000.00 .183400000 9300000.00 .2500000008230 3 16 81 9500000.00 .381000000 9700000.00 .509200000 9900000.00 .6344000008230 3 16 82 10000000.0 .696000000 10100000.0 .761200000 10300000.0 .8864000008230 3 16 83 10500000.0 1.00500000 10700000.0 1.11700000 10900000.0 1.222000008230 3 16 84 11100000.0 1.32000000 11300000.0 1.41200000 11500000.0 1.497000008230 3 16 85 11700000.0 1.57500000 11900000.0 1.64700000 12000000.0 1.680000008230 3 16 86 12300000.0 1.76200000 12600000.0 1.83600000 12900000.0 1.900000008230 3 16 87 13200000.0 1.95500000 13600000.0 2.01600000 14000000.0 2.064000008230 3 16 88 14500000.0 2.10300000 15200000.0 2.14100000 15600000.0 2.152000008230 3 16 89 15800000.0 2.15200000 16200000.0 2.14000000 16600000.0 2.115000008230 3 16 90 17000000.0 2.07600000 17400000.0 2.02400000 17700000.0 1.976000008230 3 16 91 18300000.0 1.86100000 18600000.0 1.79000000 18800000.0 1.738000008230 3 16 92 19000000.0 1.68000000 19400000.0 1.52900000 19800000.0 1.387000008230 3 16 93 20000000.0 1.32000000 8230 3 16 94 8230 3 0 95 8.22040E+4 2.02221E+2 0 0 0 08230 3103 96 2.93000E+2 1.80000E+4 0 0 1 178230 3103 97 17 2 8230 3103 98 10390000.0 0.0 10690000.0 5.91900E-5 10990000.0 .0002305008230 3103 99 11290000.0 .000496300 11590000.0 .000830300 12490000.0 .0019450008230 3103 100 12790000.0 .002270000 13090000.0 .002546000 13690000.0 .0029420008230 3103 101 14290000.0 .003160000 14890000.0 .003260000 16690000.0 .0033170008230 3103 102 16990000.0 .003300000 17590000.0 .003145000 19390000.0 .0022550008230 3103 103 19990000.0 .002017000 20000000.0 .002017000 8230 3103 104 8230 3 0 105 8230 0 0 106 0 0 0 107 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0