IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 3.80860E+4 8.51713E+1 0 0 1 13850 1451 1 0.0 0.0 0 0 0 03850 1451 2 0.0 0.0 0 0 48 23850 1451 3 38-Sr- 86 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.3850 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 3850 1451 5 IDENTIFIER=INDL 3850 REV1 3850 1451 6 FORMAT= ENDF/B-5 3850 1451 7 HISTORY= 3850 1451 8 840217 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 3850 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 3850 1451 10 TEXT= 3850 1451 11 38-SR-86(N,P)37-RB-86-M+G EN.REG.UP TO 20.MEV IN 100.KEV STEPS 3850 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 3850 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 3850 1451 14 OBNINSK,USSR). 3850 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 3850 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 3850 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 3850 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 3850 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 3850 1451 20 KONSTANTY,32(1),PAGE 105,1979 3850 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 3850 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 3850 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 3850 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 3850 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 3850 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 3850 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.3850 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 3850 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 3850 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 3850 1451 31 -------------|-------------|---------------|------------------ 3850 1451 32 38-SR-86(N,P) | 0.11 | | 3850 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************3850 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 3850 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 3850 1451 36 ***************** Program FIXUP (Version 2002-1) ****************3850 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 3850 1451 38 Corrected Thresholds-----------------------------------------Yes 3850 1451 39 Extended Cross Sections to 20 MeV----------------------------No 3850 1451 40 Allow Cross Section Deletion---------------------------------No 3850 1451 41 Allow Cross Section Reconstruction---------------------------No 3850 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 3850 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 3850 1451 44 Deleted Duplicate Points-------------------------------------Yes 3850 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 3850 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 3850 1451 47 Allow Creation of Missing Sections---------------------------No 3850 1451 48 Allow Insertion of Energy Points-----------------------------No 3850 1451 49 Create Uniform Energy Grid-----------------------------------No 3850 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 3850 1451 51 1 451 53 13850 1451 52 3 103 8 13850 1451 53 3850 1 0 54 3850 0 0 55 3.80860E+4 8.51713E+1 0 1 0 03850 3103 56 2.93000E+2-9.89000E+5 0 0 1 153850 3103 57 15 2 3850 3103 58 1000611.89 0.0 5000000.00 0.0 6000000.00 .0007000003850 3103 59 7000000.00 .002000000 8000000.00 .005000000 9000000.00 .0090000003850 3103 60 10000000.0 .014000000 12000000.0 .028000000 13000000.0 .0360000003850 3103 61 14000000.0 .042000000 15000000.0 .046000000 16000000.0 .0490000003850 3103 62 17000000.0 .050000000 18000000.0 .050000000 20000000.0 .0480000003850 3103 63 3850 3 0 64 3850 0 0 65 0 0 0 66 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0