IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 3.80880E+4 8.71505E+1 0 0 1 13840 1451 1 0.0 0.0 0 0 0 03840 1451 2 0.0 0.0 0 0 48 33840 1451 3 38-Sr- 88 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.3840 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 3840 1451 5 IDENTIFIER=INDL 3840 REV1 3840 1451 6 FORMAT= ENDF/B-5 3840 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 3840 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 3840 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 3840 1451 10 TEXT= 3840 1451 11 38-SR-88(N,2N)38-SR-87M EN.REG.UP TO 20.MEV IN 100.KEV STEPS 3840 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 3840 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 3840 1451 14 OBNINSK,USSR). 3840 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 3840 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 3840 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 3840 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 3840 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 3840 1451 20 KONSTANTY,32(1),PAGE 105,1979 3840 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 3840 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 3840 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 3840 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 3840 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 3840 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 3840 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.3840 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 3840 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 3840 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 3840 1451 31 -------------|-------------|---------------|------------------ 3840 1451 32 38-SR-88(N,2N)M| 0.0451 | 0.037 | 0.0626 3840 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************3840 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 3840 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 3840 1451 36 ***************** Program FIXUP (Version 2002-1) ****************3840 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 3840 1451 38 Corrected Thresholds-----------------------------------------Yes 3840 1451 39 Extended Cross Sections to 20 MeV----------------------------No 3840 1451 40 Allow Cross Section Deletion---------------------------------No 3840 1451 41 Allow Cross Section Reconstruction---------------------------No 3840 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 3840 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 3840 1451 44 Deleted Duplicate Points-------------------------------------Yes 3840 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 3840 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 3840 1451 47 Allow Creation of Missing Sections---------------------------No 3840 1451 48 Allow Insertion of Energy Points-----------------------------No 3840 1451 49 Create Uniform Energy Grid-----------------------------------No 3840 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 3840 1451 51 1 451 54 13840 1451 52 3 26 15 13840 1451 53 3 103 7 13840 1451 54 3840 1 0 55 3840 0 0 56 3.80880E+4 8.71505E+1 0 1 0 03840 3 26 57 2.93000E+2-1.15000E+7 0 0 1 343840 3 26 58 34 2 3840 3 26 59 11631955.6 0.0 11700000.0 .017000000 12000000.0 .0440000003840 3 26 60 12300000.0 .078380000 12700000.0 .124800000 13000000.0 .1600000003840 3 26 61 13100000.0 .174800000 13200000.0 .189000000 13300000.0 .2025000003840 3 26 62 13400000.0 .215400000 13500000.0 .227700000 13600000.0 .2394000003840 3 26 63 13700000.0 .250500000 13800000.0 .261000000 13900000.0 .2708000003840 3 26 64 14000000.0 .280000000 14200000.0 .294200000 14400000.0 .3070000003840 3 26 65 14600000.0 .318600000 14800000.0 .329000000 15000000.0 .3380000003840 3 26 66 15300000.0 .347500000 15700000.0 .357900000 16000000.0 .3640000003840 3 26 67 16600000.0 .370800000 17300000.0 .376200000 17800000.0 .3774000003840 3 26 68 18000000.0 .377000000 18200000.0 .377800000 18500000.0 .3765000003840 3 26 69 18800000.0 .372400000 19000000.0 .368000000 19800000.0 .3354000003840 3 26 70 20000000.0 .327000000 3840 3 26 71 3840 3 0 72 3.80880E+4 8.71505E+1 0 1 0 03840 3103 73 2.93000E+2-4.52200E+6 0 0 1 113840 3103 74 11 2 3840 3103 75 4574000.00 0.0 9500000.00 0.0 10000000.0 .0006000003840 3103 76 11000000.0 .002000000 12000000.0 .004000000 14000000.0 .0120000003840 3103 77 15000000.0 .018000000 16000000.0 .023000000 17000000.0 .0270000003840 3103 78 19000000.0 .031000000 20000000.0 .032000000 3840 3103 79 3840 3 0 80 3840 0 0 81 0 0 0 82 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0