IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 1.60340E+4 3.36761E+1 0 0 1 11640 1451 1 0.0 0.0 0 0 0 01640 1451 2 0.0 0.0 0 0 48 31640 1451 3 16-S - 34 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.1640 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 1640 1451 5 IDENTIFIER=INDL 1640 REV1 1640 1451 6 FORMAT= ENDF/B-5 1640 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 1640 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 1640 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 1640 1451 10 TEXT= 1640 1451 11 16-S-34(N,A)14-SI-31 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 1640 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 1640 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 1640 1451 14 OBNINSK,USSR). 1640 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 1640 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 1640 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 1640 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 1640 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 1640 1451 20 KONSTANTY,32(1),PAGE 105,1979 1640 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 1640 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 1640 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 1640 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 1640 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 1640 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 1640 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.1640 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 1640 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 1640 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 1640 1451 31 -------------|-------------|---------------|------------------ 1640 1451 32 16-S-34(N,A) | 2.30 | 2.14 | 2.29 1640 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************1640 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 1640 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 1640 1451 36 ***************** Program FIXUP (Version 2002-1) ****************1640 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 1640 1451 38 Corrected Thresholds-----------------------------------------Yes 1640 1451 39 Extended Cross Sections to 20 MeV----------------------------No 1640 1451 40 Allow Cross Section Deletion---------------------------------No 1640 1451 41 Allow Cross Section Reconstruction---------------------------No 1640 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 1640 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 1640 1451 44 Deleted Duplicate Points-------------------------------------Yes 1640 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 1640 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 1640 1451 47 Allow Creation of Missing Sections---------------------------No 1640 1451 48 Allow Insertion of Energy Points-----------------------------No 1640 1451 49 Create Uniform Energy Grid-----------------------------------No 1640 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 1640 1451 51 1 451 54 11640 1451 52 3 103 9 11640 1451 53 3 107 26 11640 1451 54 1640 1 0 55 1640 0 0 56 1.60340E+4 3.36761E+1 0 0 0 01640 3103 57 2.93000E+2-4.32000E+6 0 0 1 161640 3103 58 16 2 1640 3103 59 4448000.00 0.0 5800000.00 0.0 6500000.00 .0110000001640 3103 60 7000000.00 .022000000 8000000.00 .047000000 9000000.00 .0660000001640 3103 61 10000000.0 .080000000 11000000.0 .087000000 12000000.0 .0900000001640 3103 62 13000000.0 .087000000 14000000.0 .078000000 15000000.0 .0680000001640 3103 63 16000000.0 .055000000 18000000.0 .025000000 19000000.0 .0180000001640 3103 64 20000000.0 .013000000 1640 3103 65 1640 3 0 66 1.60340E+4 3.36761E+1 0 0 0 01640 3107 67 2.93000E+2-1.33000E+6 0 0 1 681640 3107 68 68 2 1640 3107 69 1369493.88 0.0 4900000.00 0.0 5000000.00 .0010000001640 3107 70 5100000.00 .003865000 5200000.00 .006760000 5300000.00 .0096850001640 3107 71 5500000.00 .015620000 5700000.00 .021680000 5900000.00 .0278600001640 3107 72 6200000.00 .037360000 6500000.00 .047120000 6800000.00 .0571600001640 3107 73 7000000.00 .064000000 7200000.00 .071760000 7500000.00 .0828700001640 3107 74 7800000.00 .093360000 8100000.00 .103200000 8300000.00 .1094000001640 3107 75 8500000.00 .115400000 8800000.00 .123800000 9200000.00 .1340000001640 3107 76 9500000.00 .140900000 9800000.00 .147200000 10200000.0 .1548000001640 3107 77 10500000.0 .159700000 10800000.0 .163800000 11200000.0 .1680000001640 3107 78 11500000.0 .170000000 11800000.0 .171000000 12000000.0 .1710000001640 3107 79 12300000.0 .170200000 12600000.0 .168200000 12800000.0 .1664000001640 3107 80 13000000.0 .164000000 13500000.0 .155000000 14000000.0 .1450000001640 3107 81 14500000.0 .134000000 15000000.0 .122000000 15400000.0 .1114000001640 3107 82 15900000.0 .097790000 16100000.0 .092050000 16900000.0 .0688500001640 3107 83 17000000.0 .066000000 17200000.0 .059600000 17400000.0 .0536000001640 3107 84 17600000.0 .048000000 17700000.0 .045350000 17800000.0 .0428000001640 3107 85 17900000.0 .040350000 18000000.0 .038000000 18200000.0 .0339200001640 3107 86 18400000.0 .030080000 18500000.0 .028250000 18600000.0 .0264800001640 3107 87 18700000.0 .024770000 18800000.0 .023120000 18900000.0 .0215300001640 3107 88 19000000.0 .020000000 19100000.0 .018620000 19200000.0 .0172800001640 3107 89 19300000.0 .015980000 19400000.0 .014720000 19500000.0 .0135000001640 3107 90 19600000.0 .012320000 19700000.0 .011180000 19800000.0 .0100800001640 3107 91 19900000.0 .009020000 20000000.0 .008000000 1640 3107 92 1640 3 0 93 1640 0 0 94 0 0 0 95 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0