IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 3.20700E+4 6.93238E+1 0 0 1 13230 1451 1 0.0 0.0 0 0 0 03230 1451 2 0.0 0.0 0 0 67 33230 1451 3 32-Ge- 70 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.3230 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 3230 1451 5 IDENTIFIER=INDL 3230 REV1 3230 1451 6 FORMAT= ENDF/B-5 3230 1451 7 =============================================================== 3230 1451 8 ======================== For MF = 16 ======================== 3230 1451 9 3230 1451 10 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 3230 1451 11 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 3230 1451 12 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 3230 1451 13 TEXT= 3230 1451 14 32-GE-70(N,2N)32-GE-69 EN.REG. UP TO 20.MEV IN STEPS OF 100.KEV 3230 1451 15 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 3230 1451 16 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 3230 1451 17 OBNINSK,USSR). 3230 1451 18 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 3230 1451 19 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 3230 1451 20 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 3230 1451 21 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 3230 1451 22 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 3230 1451 23 KONSTANTY,32(1),PAGE 105,1979 3230 1451 24 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 3230 1451 25 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 3230 1451 26 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 3230 1451 27 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 3230 1451 28 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 3230 1451 29 YAD. KOSTANTY 3,(42),P.60,(1981) 3230 1451 30 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.3230 1451 31 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 3230 1451 32 REACTION | V.2,P.271,IAEA,VIENNA) 3230 1451 33 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 3230 1451 34 -------------|-------------|---------------|------------------ 3230 1451 35 32-GE-70(N,2N) | 0.073 | 0.060 | 0.104 3230 1451 36 =============================================================== 3230 1451 37 ======================== For MF = 103 ======================== 3230 1451 38 0.32070E 05 0.6932E 02 0 0 1 13230 1451 39 0.0 0.0 0 0 0 03230 1451 40 0.0 0.0 0 0 9 23230 1451 41 32-Ge- 70 1USALRL EVAL- 82 3230 1451 42 3230 1451 43 IDENTIFIER=ENDL 3235 3230 1451 44 FORMAT= ENDF/B-5 3230 1451 45 HISTORY= 840315 DATA WERE CONVERTED IN ENDF/B-5 FORMAT BY NDS 3230 1451 46 3230 1451 47 TEXT= 3230 1451 48 THIS EVALUATED CROSS-SECTION WAS TAKEN FROM LIVERMORE ACTIVATION 3230 1451 49 LIBRARY 3230 1451 50 3230 1451 51 =============================================================== 3230 1451 52 ***************** Program LINEAR (VERSION 2002-1) ***************3230 1451 53 For All Data Greater than 1.0000E-10 barns in Absolute Value 3230 1451 54 Data Linearized to Within an Accuracy of .100000000 per-cent 3230 1451 55 ***************** Program FIXUP (Version 2002-1) ****************3230 1451 56 Corrected ZA/AWR in All Sections-----------------------------Yes 3230 1451 57 Corrected Thresholds-----------------------------------------Yes 3230 1451 58 Extended Cross Sections to 20 MeV----------------------------No 3230 1451 59 Allow Cross Section Deletion---------------------------------No 3230 1451 60 Allow Cross Section Reconstruction---------------------------No 3230 1451 61 Make All Cross Sections Non-Negative-------------------------Yes 3230 1451 62 Delete Energies Not in Ascending Order-----------------------Yes 3230 1451 63 Deleted Duplicate Points-------------------------------------Yes 3230 1451 64 Check for Ascending MAT/MF/MT Order--------------------------Yes 3230 1451 65 Check for Legal MF/MT Numbers--------------------------------Yes 3230 1451 66 Allow Creation of Missing Sections---------------------------No 3230 1451 67 Allow Insertion of Energy Points-----------------------------No 3230 1451 68 Create Uniform Energy Grid-----------------------------------No 3230 1451 69 Delete Section if Cross Section =0 at All Energies-----------Yes 3230 1451 70 1 451 73 13230 1451 71 3 16 14 13230 1451 72 3 103 10 13230 1451 73 3230 1 0 74 3230 0 0 75 3.20700E+4 6.93238E+1 0 0 0 03230 3 16 76 2.93000E+2-1.15300E+7 0 0 1 333230 3 16 77 33 2 3230 3 16 78 11696320.9 0.0 12000000.0 0.0 12100000.0 .0180000003230 3 16 79 12200000.0 .045000000 12300000.0 .075000000 12400000.0 .1100000003230 3 16 80 12700000.0 .200000000 12800000.0 .225000000 12900000.0 .2520000003230 3 16 81 13000000.0 .285000000 13200000.0 .336000000 13400000.0 .3844000003230 3 16 82 13600000.0 .430400000 13800000.0 .474000000 14000000.0 .5150000003230 3 16 83 14300000.0 .570800000 14600000.0 .621900000 14900000.0 .6685000003230 3 16 84 15200000.0 .711000000 15500000.0 .748600000 15800000.0 .7812000003230 3 16 85 16000000.0 .800000000 16300000.0 .823200000 16600000.0 .8420000003230 3 16 86 16900000.0 .856200000 17000000.0 .860000000 17500000.0 .8675000003230 3 16 87 18200000.0 .870800000 18600000.0 .868200000 19000000.0 .8600000003230 3 16 88 19400000.0 .838400000 19800000.0 .821600000 20000000.0 .8150000003230 3 16 89 3230 3 0 90 3.20700E+4 6.93238E+1 0 0 0 03230 3103 91 2.93000E+2-8.74000E+5 0 0 1 213230 3103 92 21 2 3230 3103 93 886607.503 0.0 5490000.00 0.0 5790000.00 .0027490003230 3103 94 6090000.00 .010520000 6390000.00 .022010000 6990000.00 .0490700003230 3103 95 7290000.00 .061420000 7590000.00 .071620000 7890000.00 .0793700003230 3103 96 8190000.00 .084810000 8790000.00 .090530000 9390000.00 .0924200003230 3103 97 12990000.0 .093000000 13290000.0 .092500000 13890000.0 .0869900003230 3103 98 15390000.0 .062170000 15690000.0 .058140000 16290000.0 .0522600003230 3103 99 16890000.0 .048970000 17490000.0 .047410000 20000000.0 .0465000003230 3103 100 3230 3 0 101 3230 0 0 102 0 0 0 103 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0