IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 3.50790E+4 7.82404E+1 0 0 1 13530 1451 1 0.0 0.0 0 0 0 03530 1451 2 0.0 0.0 0 0 48 33530 1451 3 35-Br- 79 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.3530 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 3530 1451 5 IDENTIFIER=INDL 3530 REV1 3530 1451 6 FORMAT= ENDF/B-5 3530 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 3530 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 3530 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 3530 1451 10 TEXT= 3530 1451 11 35-BR-79(N,2N)35-BR-78 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 3530 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 3530 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 3530 1451 14 OBNINSK,USSR). 3530 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 3530 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 3530 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 3530 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 3530 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 3530 1451 20 KONSTANTY,32(1),PAGE 105,1979 3530 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 3530 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 3530 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 3530 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 3530 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 3530 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 3530 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.3530 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 3530 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 3530 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 3530 1451 31 -------------|-------------|---------------|------------------ 3530 1451 32 35-BR-79(N,2N) | 0.204 | 0.169 | 0.272 3530 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************3530 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 3530 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 3530 1451 36 ***************** Program FIXUP (Version 2002-1) ****************3530 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 3530 1451 38 Corrected Thresholds-----------------------------------------Yes 3530 1451 39 Extended Cross Sections to 20 MeV----------------------------No 3530 1451 40 Allow Cross Section Deletion---------------------------------No 3530 1451 41 Allow Cross Section Reconstruction---------------------------No 3530 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 3530 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 3530 1451 44 Deleted Duplicate Points-------------------------------------Yes 3530 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 3530 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 3530 1451 47 Allow Creation of Missing Sections---------------------------No 3530 1451 48 Allow Insertion of Energy Points-----------------------------No 3530 1451 49 Create Uniform Energy Grid-----------------------------------No 3530 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 3530 1451 51 1 451 54 13530 1451 52 3 16 14 13530 1451 53 3 107 8 13530 1451 54 3530 1 0 55 3530 0 0 56 3.50790E+4 7.82404E+1 0 1 0 03530 3 16 57 2.93000E+2-1.06900E+7 0 0 1 333530 3 16 58 33 2 3530 3 16 59 10826630.2 0.0 10900000.0 0.0 11000000.0 .0100000003530 3 16 60 11100000.0 .040550000 11300000.0 .101900000 11600000.0 .1948000003530 3 16 61 12000000.0 .320000000 12200000.0 .389600000 12400000.0 .4564000003530 3 16 62 12600000.0 .520400000 12800000.0 .581600000 13200000.0 .6986000003530 3 16 63 13400000.0 .752800000 13600000.0 .802800000 13800000.0 .8486000003530 3 16 64 14000000.0 .890000000 14200000.0 .926800000 14400000.0 .9596000003530 3 16 65 14600000.0 .988200000 14800000.0 1.01300000 15000000.0 1.033000003530 3 16 66 15300000.0 1.05100000 15700000.0 1.06700000 16100000.0 1.074000003530 3 16 67 16400000.0 1.07400000 16800000.0 1.06600000 17000000.0 1.060000003530 3 16 68 17400000.0 1.03800000 17800000.0 1.01200000 18200000.0 .9822000003530 3 16 69 18800000.0 .929400000 19000000.0 .910000000 20000000.0 .8000000003530 3 16 70 3530 3 0 71 3.50790E+4 7.82404E+1 0 1 0 03530 3107 72 2.93000E+2 1.85900E+6 0 0 1 143530 3107 73 14 2 3530 3107 74 100000.000 0.0 6800000.00 0.0 7500000.00 .0003000003530 3107 75 8000000.00 .000500000 9000000.00 .001000000 10000000.0 .0020000003530 3107 76 11000000.0 .004000000 13000000.0 .010000000 14000000.0 .0120000003530 3107 77 15000000.0 .012000000 16000000.0 .011000000 17000000.0 .0080000003530 3107 78 19000000.0 .004000000 20000000.0 .003000000 3530 3107 79 3530 3 0 80 3530 0 0 81 0 0 0 82 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0