IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 6.21440E+4 1.42676E+2 0 0 1 16230 1451 1 0.0 0.0 0 0 0 06230 1451 2 0.0 0.0 0 0 48 26230 1451 3 62-Sm-144 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.6230 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 6230 1451 5 IDENTIFIER=INDL 6230 REV1 6230 1451 6 FORMAT= ENDF/B-5 6230 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 6230 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 6230 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 6230 1451 10 TEXT= 6230 1451 11 62-SM-144(N,2N)62-SM-143 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 6230 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 6230 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 6230 1451 14 OBNINSK,USSR). 6230 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 6230 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 6230 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 6230 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 6230 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 6230 1451 20 KONSTANTY,32(1),PAGE 105,1979 6230 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 6230 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 6230 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 6230 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 6230 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 6230 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 6230 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.6230 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 6230 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 6230 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 6230 1451 31 -------------|-------------|---------------|------------------ 6230 1451 32 62-SM-144(N,2N) | 0.369 | 0.308 | 0.490 6230 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************6230 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 6230 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 6230 1451 36 ***************** Program FIXUP (Version 2002-1) ****************6230 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 6230 1451 38 Corrected Thresholds-----------------------------------------Yes 6230 1451 39 Extended Cross Sections to 20 MeV----------------------------No 6230 1451 40 Allow Cross Section Deletion---------------------------------No 6230 1451 41 Allow Cross Section Reconstruction---------------------------No 6230 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 6230 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 6230 1451 44 Deleted Duplicate Points-------------------------------------Yes 6230 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 6230 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 6230 1451 47 Allow Creation of Missing Sections---------------------------No 6230 1451 48 Allow Insertion of Energy Points-----------------------------No 6230 1451 49 Create Uniform Energy Grid-----------------------------------No 6230 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 6230 1451 51 1 451 53 16230 1451 52 3 16 14 16230 1451 53 6230 1 0 54 6230 0 0 55 6.21440E+4 1.42676E+2 0 1 0 06230 3 16 56 2.93000E+2-1.05500E+7 0 0 1 316230 3 16 57 31 2 6230 3 16 58 10623943.8 0.0 10900000.0 0.0 11000000.0 .0500000006230 3 16 59 11100000.0 .117400000 11200000.0 .183200000 11300000.0 .2473000006230 3 16 60 11400000.0 .309800000 11500000.0 .370600000 11600000.0 .4298000006230 3 16 61 11700000.0 .487300000 11800000.0 .543200000 11900000.0 .5974000006230 3 16 62 12000000.0 .650000000 12200000.0 .746600000 12400000.0 .8384000006230 3 16 63 12600000.0 .925400000 12800000.0 1.00800000 13200000.0 1.160000006230 3 16 64 13400000.0 1.23000000 13600000.0 1.29300000 13800000.0 1.349000006230 3 16 65 14000000.0 1.40000000 14400000.0 1.47200000 14800000.0 1.533000006230 3 16 66 15000000.0 1.56000000 16200000.0 1.67400000 16800000.0 1.725000006230 3 16 67 17400000.0 1.76600000 18100000.0 1.80500000 19000000.0 1.840000006230 3 16 68 20000000.0 1.86000000 6230 3 16 69 6230 3 0 70 6230 0 0 71 0 0 0 72 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0