IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 3.00680E+4 6.73414E+1 0 0 1 13070 1451 1 0.0 0.0 0 0 0 03070 1451 2 0.0 0.0 0 0 48 23070 1451 3 30-Zn- 68 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.3070 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 3070 1451 5 IDENTIFIER=INDL 3070 REV1 3070 1451 6 FORMAT= ENDF/B-5 3070 1451 7 HISTORY= 3070 1451 8 840220 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 3070 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 3070 1451 10 TEXT= 3070 1451 11 30-ZN-68(N,A)28-NI-65 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 3070 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 3070 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 3070 1451 14 OBNINSK,USSR). 3070 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 3070 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 3070 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 3070 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 3070 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 3070 1451 20 KONSTANTY,32(1),PAGE 105,1979 3070 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 3070 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 3070 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 3070 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 3070 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 3070 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 3070 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.3070 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 3070 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 3070 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 3070 1451 31 -------------|-------------|---------------|------------------ 3070 1451 32 30-ZN-68(N,A) | 0.074 | | 3070 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************3070 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 3070 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 3070 1451 36 ***************** Program FIXUP (Version 2002-1) ****************3070 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 3070 1451 38 Corrected Thresholds-----------------------------------------Yes 3070 1451 39 Extended Cross Sections to 20 MeV----------------------------No 3070 1451 40 Allow Cross Section Deletion---------------------------------No 3070 1451 41 Allow Cross Section Reconstruction---------------------------No 3070 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 3070 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 3070 1451 44 Deleted Duplicate Points-------------------------------------Yes 3070 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 3070 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 3070 1451 47 Allow Creation of Missing Sections---------------------------No 3070 1451 48 Allow Insertion of Energy Points-----------------------------No 3070 1451 49 Create Uniform Energy Grid-----------------------------------No 3070 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 3070 1451 51 1 451 53 13070 1451 52 3 107 7 13070 1451 53 3070 1 0 54 3070 0 0 55 3.00680E+4 6.73414E+1 0 0 0 03070 3107 56 2.93000E+2 7.76000E+5 0 0 1 123070 3107 57 12 2 3070 3107 58 100000.000 0.0 6500000.00 0.0 7000000.00 .0006000003070 3107 59 7500000.00 .001100000 8000000.00 .002000000 9000000.00 .0030000003070 3107 60 10000000.0 .004500000 11000000.0 .008000000 15000000.0 .0120000003070 3107 61 18000000.0 .006000000 19000000.0 .004500000 20000000.0 .0038000003070 3107 62 3070 3 0 63 3070 0 0 64 0 0 0 65 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0