IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 6.21540E+4 1.52600E+2 0 0 1 16270 1451 1 0.0 0.0 0 0 0 06270 1451 2 0.0 0.0 0 0 48 26270 1451 3 62-Sm-154 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.6270 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 6270 1451 5 IDENTIFIER=INDL 6270 REV1 6270 1451 6 FORMAT= ENDF/B-5 6270 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 6270 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 6270 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 6270 1451 10 TEXT= 6270 1451 11 62-SM-154(N,2N)62-SM-153 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 6270 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 6270 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 6270 1451 14 OBNINSK,USSR). 6270 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 6270 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 6270 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 6270 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 6270 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 6270 1451 20 KONSTANTY,32(1),PAGE 105,1979 6270 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 6270 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 6270 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 6270 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 6270 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 6270 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 6270 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.6270 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 6270 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 6270 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 6270 1451 31 -------------|-------------|---------------|------------------ 6270 1451 32 62-SM-154(N,2N) | 3.90 | 3.45 | 4.34 6270 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************6270 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 6270 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 6270 1451 36 ***************** Program FIXUP (Version 2002-1) ****************6270 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 6270 1451 38 Corrected Thresholds-----------------------------------------Yes 6270 1451 39 Extended Cross Sections to 20 MeV----------------------------No 6270 1451 40 Allow Cross Section Deletion---------------------------------No 6270 1451 41 Allow Cross Section Reconstruction---------------------------No 6270 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 6270 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 6270 1451 44 Deleted Duplicate Points-------------------------------------Yes 6270 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 6270 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 6270 1451 47 Allow Creation of Missing Sections---------------------------No 6270 1451 48 Allow Insertion of Energy Points-----------------------------No 6270 1451 49 Create Uniform Energy Grid-----------------------------------No 6270 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 6270 1451 51 1 451 53 16270 1451 52 3 16 17 16270 1451 53 6270 1 0 54 6270 0 0 55 6.21540E+4 1.52600E+2 0 1 0 06270 3 16 56 2.93000E+2-7.98000E+6 0 0 1 406270 3 16 57 40 2 6270 3 16 58 8032293.58 0.0 8100000.00 .058100000 8300000.00 .1749000006270 3 16 59 8600000.00 .351600000 9000000.00 .590000000 9100000.00 .6658000006270 3 16 60 9200000.00 .738400000 9300000.00 .807600000 9400000.00 .8736000006270 3 16 61 9500000.00 .936200000 9600000.00 .995600000 9700000.00 1.052000006270 3 16 62 9900000.00 1.15400000 10000000.0 1.20000000 10200000.0 1.262000006270 3 16 63 10500000.0 1.34900000 10800000.0 1.43000000 11300000.0 1.555000006270 3 16 64 11600000.0 1.61900000 11800000.0 1.65700000 12000000.0 1.690000006270 3 16 65 12600000.0 1.75400000 13100000.0 1.80100000 13400000.0 1.830000006270 3 16 66 13700000.0 1.84900000 14200000.0 1.86800000 14400000.0 1.870000006270 3 16 67 14600000.0 1.86400000 14900000.0 1.84100000 15000000.0 1.830000006270 3 16 68 15600000.0 1.70800000 16100000.0 1.59600000 17000000.0 1.380000006270 3 16 69 17300000.0 1.30200000 17500000.0 1.25200000 17900000.0 1.161000006270 3 16 70 18200000.0 1.10100000 18500000.0 1.04500000 19000000.0 .9600000006270 3 16 71 20000000.0 .816000000 6270 3 16 72 6270 3 0 73 6270 0 0 74 0 0 0 75 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0