IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 6.21520E+4 1.50615E+2 0 0 1 16260 1451 1 0.0 0.0 0 0 0 06260 1451 2 0.0 0.0 0 0 48 26260 1451 3 62-Sm-152 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.6260 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 6260 1451 5 IDENTIFIER=INDL 6260 REV1 6260 1451 6 FORMAT= ENDF/B-5 6260 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 6260 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 6260 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 6260 1451 10 TEXT= 6260 1451 11 62-SM-152(N,2N)62-SM-151 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 6260 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 6260 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 6260 1451 14 OBNINSK,USSR). 6260 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 6260 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 6260 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 6260 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 6260 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 6260 1451 20 KONSTANTY,32(1),PAGE 105,1979 6260 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 6260 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 6260 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 6260 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 6260 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 6260 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 6260 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.6260 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 6260 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 6260 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 6260 1451 31 -------------|-------------|---------------|------------------ 6260 1451 32 62-SM-152(N,2N) | 2.34 | 2.05 | 2.69 6260 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************6260 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 6260 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 6260 1451 36 ***************** Program FIXUP (Version 2002-1) ****************6260 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 6260 1451 38 Corrected Thresholds-----------------------------------------Yes 6260 1451 39 Extended Cross Sections to 20 MeV----------------------------No 6260 1451 40 Allow Cross Section Deletion---------------------------------No 6260 1451 41 Allow Cross Section Reconstruction---------------------------No 6260 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 6260 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 6260 1451 44 Deleted Duplicate Points-------------------------------------Yes 6260 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 6260 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 6260 1451 47 Allow Creation of Missing Sections---------------------------No 6260 1451 48 Allow Insertion of Energy Points-----------------------------No 6260 1451 49 Create Uniform Energy Grid-----------------------------------No 6260 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 6260 1451 51 1 451 53 16260 1451 52 3 16 18 16260 1451 53 6260 1 0 54 6260 0 0 55 6.21520E+4 1.50615E+2 0 1 0 06260 3 16 56 2.93000E+2-8.27000E+6 0 0 1 446260 3 16 57 44 2 6260 3 16 58 8324908.21 0.0 8500000.00 0.0 8700000.00 .0700000006260 3 16 59 8800000.00 .120000000 8900000.00 .160000000 9000000.00 .2100000006260 3 16 60 9100000.00 .273900000 9200000.00 .336800000 9300000.00 .3985000006260 3 16 61 9400000.00 .459200000 9600000.00 .577200000 9800000.00 .6908000006260 3 16 62 10000000.0 .800000000 10100000.0 .857400000 10200000.0 .9128000006260 3 16 63 10300000.0 .966000000 10500000.0 1.06600000 10700000.0 1.158000006260 3 16 64 10800000.0 1.20100000 11000000.0 1.28000000 11300000.0 1.373000006260 3 16 65 11600000.0 1.45500000 11800000.0 1.50500000 12000000.0 1.550000006260 3 16 66 12300000.0 1.60500000 12600000.0 1.65400000 12900000.0 1.697000006260 3 16 67 13300000.0 1.75100000 13600000.0 1.78000000 13900000.0 1.797000006260 3 16 68 14200000.0 1.80100000 14500000.0 1.79400000 14800000.0 1.777000006260 3 16 69 15000000.0 1.76000000 15500000.0 1.69100000 16000000.0 1.610000006260 3 16 70 17000000.0 1.41000000 17400000.0 1.32000000 17800000.0 1.238000006260 3 16 71 18000000.0 1.20000000 18400000.0 1.13300000 18800000.0 1.070000006260 3 16 72 19000000.0 1.04000000 20000000.0 .907000000 6260 3 16 73 6260 3 0 74 6260 0 0 75 0 0 0 76 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0