IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 3.80840E+4 8.31926E+1 0 0 1 13830 1451 1 0.0 0.0 0 0 0 03830 1451 2 0.0 0.0 0 0 48 23830 1451 3 38-Sr- 84 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.3830 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 3830 1451 5 IDENTIFIER=INDL 3830 REV1 3830 1451 6 FORMAT= ENDF/B-5 3830 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 3830 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 3830 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 3830 1451 10 TEXT= 3830 1451 11 38-SR-84(N,2N)38-SR-83 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 3830 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 3830 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 3830 1451 14 OBNINSK,USSR). 3830 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 3830 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 3830 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 3830 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 3830 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 3830 1451 20 KONSTANTY,32(1),PAGE 105,1979 3830 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 3830 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 3830 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 3830 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 3830 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 3830 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 3830 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.3830 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 3830 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 3830 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 3830 1451 31 -------------|-------------|---------------|------------------ 3830 1451 32 38-SR-84(N,2N) | 0.10 | 0.08 | 0.15 3830 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************3830 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 3830 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 3830 1451 36 ***************** Program FIXUP (Version 2002-1) ****************3830 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 3830 1451 38 Corrected Thresholds-----------------------------------------Yes 3830 1451 39 Extended Cross Sections to 20 MeV----------------------------No 3830 1451 40 Allow Cross Section Deletion---------------------------------No 3830 1451 41 Allow Cross Section Reconstruction---------------------------No 3830 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 3830 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 3830 1451 44 Deleted Duplicate Points-------------------------------------Yes 3830 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 3830 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 3830 1451 47 Allow Creation of Missing Sections---------------------------No 3830 1451 48 Allow Insertion of Energy Points-----------------------------No 3830 1451 49 Create Uniform Energy Grid-----------------------------------No 3830 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 3830 1451 51 1 451 53 13830 1451 52 3 16 15 13830 1451 53 3830 1 0 54 3830 0 0 55 3.80840E+4 8.31926E+1 0 1 0 03830 3 16 56 2.93000E+2-1.20100E+7 0 0 1 343830 3 16 57 34 2 3830 3 16 58 12154363.8 0.0 12200000.0 0.0 12300000.0 .0150000003830 3 16 59 12500000.0 .065000000 12600000.0 .100000000 12700000.0 .1400000003830 3 16 60 12900000.0 .230000000 13000000.0 .280000000 13100000.0 .3422000003830 3 16 61 13200000.0 .402800000 13300000.0 .461800000 13400000.0 .5192000003830 3 16 62 13500000.0 .575000000 13600000.0 .629200000 13700000.0 .6818000003830 3 16 63 13800000.0 .732800000 13900000.0 .782200000 14100000.0 .8793000003830 3 16 64 14200000.0 .926400000 14400000.0 1.01400000 14600000.0 1.092000003830 3 16 65 14800000.0 1.16000000 15000000.0 1.22000000 15200000.0 1.258000003830 3 16 66 15500000.0 1.30900000 15800000.0 1.35400000 16100000.0 1.392000003830 3 16 67 16500000.0 1.43200000 16900000.0 1.46400000 17200000.0 1.478000003830 3 16 68 17600000.0 1.49200000 18000000.0 1.50000000 18600000.0 1.501000003830 3 16 69 20000000.0 1.49500000 3830 3 16 70 3830 3 0 71 3830 0 0 72 0 0 0 73 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0