IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 8.22080E+4 2.06190E+2 0 0 1 18240 1451 1 0.0 0.0 0 0 0 08240 1451 2 0.0 0.0 0 0 48 28240 1451 3 82-Pb-208 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.8240 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 8240 1451 5 IDENTIFIER=INDL 8240 REV1 8240 1451 6 FORMAT= ENDF/B-5 8240 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 8240 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 8240 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 8240 1451 10 TEXT= 8240 1451 11 82-PB-208(N,2N)82-PB-208M EN.REG.UP TO 20.MEV IN 100.KEV STEPS 8240 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 8240 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 8240 1451 14 OBNINSK,USSR). 8240 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 8240 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 8240 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 8240 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 8240 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 8240 1451 20 KONSTANTY,32(1),PAGE 105,1979 8240 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 8240 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 8240 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 8240 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 8240 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 8240 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 8240 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.8240 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 8240 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 8240 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 8240 1451 31 -------------|-------------|---------------|------------------ 8240 1451 32 82-PB-208(N,2N)| 0.891 | 0.769 | 1.06 8240 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************8240 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 8240 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 8240 1451 36 ***************** Program FIXUP (Version 2002-1) ****************8240 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 8240 1451 38 Corrected Thresholds-----------------------------------------Yes 8240 1451 39 Extended Cross Sections to 20 MeV----------------------------No 8240 1451 40 Allow Cross Section Deletion---------------------------------No 8240 1451 41 Allow Cross Section Reconstruction---------------------------No 8240 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 8240 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 8240 1451 44 Deleted Duplicate Points-------------------------------------Yes 8240 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 8240 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 8240 1451 47 Allow Creation of Missing Sections---------------------------No 8240 1451 48 Allow Insertion of Energy Points-----------------------------No 8240 1451 49 Create Uniform Energy Grid-----------------------------------No 8240 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 8240 1451 51 1 451 53 18240 1451 52 3 26 16 18240 1451 53 8240 1 0 54 8240 0 0 55 8.22080E+4 2.06190E+2 0 1 0 08240 3 26 56 2.93000E+2-8.96000E+6 0 0 1 378240 3 26 57 37 2 8240 3 26 58 9003455.07 0.0 9100000.00 .025100000 9200000.00 .0504000008240 3 26 59 9300000.00 .075900000 9500000.00 .127500000 9700000.00 .1799000008240 3 26 60 10000000.0 .260000000 10300000.0 .341900000 10600000.0 .4256000008240 3 26 61 11000000.0 .540000000 11300000.0 .634200000 11600000.0 .7248000008240 3 26 62 11900000.0 .811800000 12000000.0 .840000000 12200000.0 .9008000008240 3 26 63 12400000.0 .957200000 12600000.0 1.00900000 12800000.0 1.057000008240 3 26 64 13100000.0 1.12000000 13300000.0 1.15600000 13500000.0 1.188000008240 3 26 65 13700000.0 1.21600000 13900000.0 1.24000000 14100000.0 1.258000008240 3 26 66 14500000.0 1.28300000 14900000.0 1.29800000 15200000.0 1.301000008240 3 26 67 15400000.0 1.30100000 15900000.0 1.29300000 16400000.0 1.275000008240 3 26 68 16900000.0 1.24700000 17500000.0 1.19900000 18100000.0 1.139000008240 3 26 69 18500000.0 1.09400000 19000000.0 1.03000000 19800000.0 .9108000008240 3 26 70 20000000.0 .880000000 8240 3 26 71 8240 3 0 72 8240 0 0 73 0 0 0 74 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0