IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 6.21480E+4 1.46644E+2 0 0 1 16240 1451 1 0.0 0.0 0 0 0 06240 1451 2 0.0 0.0 0 0 48 26240 1451 3 62-Sm-148 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.6240 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 6240 1451 5 IDENTIFIER=INDL 6240 REV1 6240 1451 6 FORMAT= ENDF/B-5 6240 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 6240 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 6240 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 6240 1451 10 TEXT= 6240 1451 11 62-SM-148(N,2N)62-SM-147 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 6240 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 6240 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 6240 1451 14 OBNINSK,USSR). 6240 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 6240 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 6240 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 6240 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 6240 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 6240 1451 20 KONSTANTY,32(1),PAGE 105,1979 6240 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 6240 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 6240 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 6240 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 6240 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 6240 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 6240 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.6240 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 6240 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 6240 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 6240 1451 31 -------------|-------------|---------------|------------------ 6240 1451 32 62-SM-148(N,2N) | 3.26 | 2.88 | 3.67 6240 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************6240 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 6240 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 6240 1451 36 ***************** Program FIXUP (Version 2002-1) ****************6240 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 6240 1451 38 Corrected Thresholds-----------------------------------------Yes 6240 1451 39 Extended Cross Sections to 20 MeV----------------------------No 6240 1451 40 Allow Cross Section Deletion---------------------------------No 6240 1451 41 Allow Cross Section Reconstruction---------------------------No 6240 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 6240 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 6240 1451 44 Deleted Duplicate Points-------------------------------------Yes 6240 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 6240 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 6240 1451 47 Allow Creation of Missing Sections---------------------------No 6240 1451 48 Allow Insertion of Energy Points-----------------------------No 6240 1451 49 Create Uniform Energy Grid-----------------------------------No 6240 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 6240 1451 51 1 451 53 16240 1451 52 3 16 19 16240 1451 53 6240 1 0 54 6240 0 0 55 6.21480E+4 1.46644E+2 0 1 0 06240 3 16 56 2.93000E+2-8.14000E+6 0 0 1 466240 3 16 57 46 2 6240 3 16 58 8195508.58 0.0 8200000.00 .020000000 8400000.00 .1000000006240 3 16 59 8700000.00 .280000000 8800000.00 .350000000 8900000.00 .4000000006240 3 16 60 9000000.00 .460000000 9100000.00 .527500000 9200000.00 .5932000006240 3 16 61 9300000.00 .656900000 9400000.00 .718800000 9500000.00 .7787000006240 3 16 62 9600000.00 .836800000 9700000.00 .892900000 9800000.00 .9472000006240 3 16 63 10000000.0 1.05000000 10200000.0 1.14700000 10400000.0 1.235000006240 3 16 64 10600000.0 1.31500000 10800000.0 1.38700000 11000000.0 1.450000006240 3 16 65 11300000.0 1.51700000 11600000.0 1.57500000 11800000.0 1.610000006240 3 16 66 12000000.0 1.64000000 12400000.0 1.68500000 12800000.0 1.721000006240 3 16 67 13100000.0 1.74000000 13700000.0 1.76300000 14400000.0 1.781000006240 3 16 68 14600000.0 1.78100000 15000000.0 1.77000000 15300000.0 1.754000006240 3 16 69 15600000.0 1.72900000 15900000.0 1.69400000 16000000.0 1.680000006240 3 16 70 16600000.0 1.56400000 17000000.0 1.48000000 17600000.0 1.338000006240 3 16 71 18100000.0 1.22900000 18500000.0 1.14700000 19000000.0 1.050000006240 3 16 72 19300000.0 .989700000 19600000.0 .934800000 19900000.0 .8853000006240 3 16 73 20000000.0 .870000000 6240 3 16 74 6240 3 0 75 6240 0 0 76 0 0 0 77 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0