IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 3.40760E+4 7.52670E+1 0 0 1 13440 1451 1 0.0 0.0 0 0 0 03440 1451 2 0.0 0.0 0 0 48 23440 1451 3 34-Se- 76 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.3440 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 3440 1451 5 IDENTIFIER=INDL 3430 REV1 3440 1451 6 FORMAT= ENDF/B-5 3440 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 3440 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 3440 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 3440 1451 10 TEXT= 3440 1451 11 34-SE-76(N,2N)34-SE-75 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 3440 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 3440 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 3440 1451 14 OBNINSK,USSR). 3440 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 3440 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 3440 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 3440 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 3440 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 3440 1451 20 KONSTANTY,32(1),PAGE 105,1979 3440 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 3440 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 3440 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 3440 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 3440 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 3440 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 3440 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.3440 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 3440 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 3440 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 3440 1451 31 -------------|-------------|---------------|------------------ 3440 1451 32 34-SE-76(N,2N) | 0.137 | 0.113 | 0.189 3440 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************3440 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 3440 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 3440 1451 36 ***************** Program FIXUP (Version 2002-1) ****************3440 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 3440 1451 38 Corrected Thresholds-----------------------------------------Yes 3440 1451 39 Extended Cross Sections to 20 MeV----------------------------No 3440 1451 40 Allow Cross Section Deletion---------------------------------No 3440 1451 41 Allow Cross Section Reconstruction---------------------------No 3440 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 3440 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 3440 1451 44 Deleted Duplicate Points-------------------------------------Yes 3440 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 3440 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 3440 1451 47 Allow Creation of Missing Sections---------------------------No 3440 1451 48 Allow Insertion of Energy Points-----------------------------No 3440 1451 49 Create Uniform Energy Grid-----------------------------------No 3440 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 3440 1451 51 1 451 53 13440 1451 52 3 16 15 13440 1451 53 3440 1 0 54 3440 0 0 55 3.40760E+4 7.52670E+1 0 1 0 03440 3 16 56 2.93000E+2-1.11600E+7 0 0 1 353440 3 16 57 35 2 3440 3 16 58 11308272.2 0.0 11500000.0 0.0 11600000.0 .0100000003440 3 16 59 11700000.0 .050000000 11800000.0 .085000000 11900000.0 .1250000003440 3 16 60 12000000.0 .160000000 12100000.0 .200500000 12200000.0 .2400000003440 3 16 61 12300000.0 .278500000 12400000.0 .316000000 12500000.0 .3525000003440 3 16 62 12600000.0 .388000000 12700000.0 .422500000 12800000.0 .4560000003440 3 16 63 12900000.0 .488500000 13000000.0 .520000000 13200000.0 .5792000003440 3 16 64 13400000.0 .634800000 13600000.0 .686800000 13800000.0 .7352000003440 3 16 65 14100000.0 .801900000 14300000.0 .842500000 14500000.0 .8787000003440 3 16 66 14700000.0 .910500000 14900000.0 .937900000 15000000.0 .9500000003440 3 16 67 15400000.0 .978900000 15800000.0 1.00100000 16100000.0 1.013000003440 3 16 68 16800000.0 1.02700000 17200000.0 1.02900000 18100000.0 1.024000003440 3 16 69 19100000.0 1.01400000 20000000.0 1.00000000 3440 3 16 70 3440 3 0 71 3440 0 0 72 0 0 0 73 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0