IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 2.80600E+4 5.94160E+1 0 0 1 22830 1451 1 0.0 0.0 0 0 0 02830 1451 2 0.0 0.0 0 0 83 22830 1451 3 28-Ni- 60 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.2830 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 2830 1451 5 IDENTIFIER=INDL 2830 REV2 2830 1451 6 FORMAT= ENDF/B-5 2830 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 2830 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 2830 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 2830 1451 10 (N,P) DATA REVISED IN COMP. WITH BOSPOR-78=INDL-2830 2830 1451 11 REV1. VP. 2830 1451 12 TEXT= 2830 1451 13 28-NI-60(N,P)27-CO-60 EN.REG. UP TO 20.MEV IN STEPS OF 100.KEV 2830 1451 14 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 2830 1451 15 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 2830 1451 16 OBNINSK,USSR). 2830 1451 17 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 2830 1451 18 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 2830 1451 19 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 2830 1451 20 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 2830 1451 21 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 2830 1451 22 KONSTANTY,32(1),PAGE 105,1979 2830 1451 23 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 2830 1451 24 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 2830 1451 25 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 2830 1451 26 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 2830 1451 27 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 2830 1451 28 YAD. KOSTANTY 3,(42),P.60,(1981) 2830 1451 29 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.2830 1451 30 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 2830 1451 31 REACTION | V.2,P.271,IAEA,VIENNA) 2830 1451 32 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 2830 1451 33 -------------|-------------|---------------|------------------ 2830 1451 34 28-NI-60(N,P) | 2.57 | 2.42 | 2.53 2830 1451 35 ================================================================= 2830 1451 36 Excitation of metastable product cannot be stored in ENDF-5 format2830 1451 37 ================================================================= 2830 1451 38 0.28060E 05 0.5942E 02 0 0 1 12830 1451 39 0.0 0.0 0 0 0 02830 1451 40 0.0 0.0 0 0 9 22830 1451 41 28-Ni- 60 1USALRL EVAL- 76 2830 1451 42 2830 1451 43 IDENTIFIER=ENDL 2836 2830 1451 44 FORMAT= ENDF/B-5 2830 1451 45 HISTORY= 840315 DATA WERE CONVERTED IN ENDF/B-5 FORMAT BY NDS 2830 1451 46 2830 1451 47 TEXT= 2830 1451 48 THIS EVALUATED CROSS-SECTION WAS TAKEN FROM LIVERMORE ACTIVATION 2830 1451 49 LIBRARY 2830 1451 50 1 451 14 12830 1451 51 3 103 10 12830 1451 52 2830 1451 53 2830 1451 54 0.28060E 05 0.5942E 02 0 1 0 02830 1451 55 0.29300E 03-0.2101E 07 0 0 1 192830 1451 56 19 2 2830 1451 57 0.2134E 07 0.0 0.3700E 07 0.0 0.3900E 07 0.0 2830 1451 58 0.4000E 07 0.4000E-04 0.5000E 07 0.6000E-02 0.6000E 07 0.1800E-012830 1451 59 0.7000E 07 0.3200E-01 0.8000E 07 0.4300E-01 0.9000E 07 0.7300E-012830 1451 60 0.1000E 08 0.8000E-01 0.1050E 08 0.8100E-01 0.1100E 08 0.8000E-012830 1451 61 0.1200E 08 0.7700E-01 0.1300E 08 0.7100E-01 0.1400E 08 0.6300E-012830 1451 62 0.1500E 08 0.5500E-01 0.1600E 08 0.4600E-01 0.1800E 08 0.3600E-012830 1451 63 0.2000E 08 0.2900E-01 0.0 0.0 0.0 0.0 2830 1451 64 2830 1451 65 2830 1451 66 2830 1451 67 ================================================================= 2830 1451 68 ***************** Program LINEAR (VERSION 2002-1) ***************2830 1451 69 For All Data Greater than 1.0000E-10 barns in Absolute Value 2830 1451 70 Data Linearized to Within an Accuracy of .100000000 per-cent 2830 1451 71 ***************** Program FIXUP (Version 2002-1) ****************2830 1451 72 Corrected ZA/AWR in All Sections-----------------------------Yes 2830 1451 73 Corrected Thresholds-----------------------------------------Yes 2830 1451 74 Extended Cross Sections to 20 MeV----------------------------No 2830 1451 75 Allow Cross Section Deletion---------------------------------No 2830 1451 76 Allow Cross Section Reconstruction---------------------------No 2830 1451 77 Make All Cross Sections Non-Negative-------------------------Yes 2830 1451 78 Delete Energies Not in Ascending Order-----------------------Yes 2830 1451 79 Deleted Duplicate Points-------------------------------------Yes 2830 1451 80 Check for Ascending MAT/MF/MT Order--------------------------Yes 2830 1451 81 Check for Legal MF/MT Numbers--------------------------------Yes 2830 1451 82 Allow Creation of Missing Sections---------------------------No 2830 1451 83 Allow Insertion of Energy Points-----------------------------No 2830 1451 84 Create Uniform Energy Grid-----------------------------------No 2830 1451 85 Delete Section if Cross Section =0 at All Energies-----------Yes 2830 1451 86 1 451 88 12830 1451 87 3 103 23 22830 1451 88 2830 1 0 89 2830 0 0 90 2.80600E+4 5.94160E+1 0 0 0 02830 3103 91 2.93000E+2-2.05000E+6 0 0 1 602830 3103 92 60 2 2830 3103 93 2084502.49 0.0 3900000.00 0.0 4000000.00 .0001000002830 3103 94 4100000.00 .000455500 4200000.00 .000952000 4300000.00 .0015890002830 3103 95 4400000.00 .002368000 4500000.00 .003287000 4600000.00 .0043480002830 3103 96 4700000.00 .005549000 4800000.00 .006892000 4900000.00 .0083750002830 3103 97 5000000.00 .010000000 5100000.00 .012220000 5200000.00 .0144800002830 3103 98 5300000.00 .016780000 5400000.00 .019120000 5600000.00 .0239200002830 3103 99 5800000.00 .028880000 6000000.00 .034000000 6300000.00 .0421400002830 3103 100 6600000.00 .050500000 7000000.00 .062000000 7300000.00 .0716700002830 3103 101 7600000.00 .080900000 7900000.00 .089670000 8200000.00 .0982000002830 3103 102 8500000.00 .106200000 8900000.00 .115800000 9200000.00 .1221000002830 3103 103 9500000.00 .127800000 9900000.00 .134500000 10300000.0 .1401000002830 3103 104 10700000.0 .144900000 11100000.0 .148900000 11500000.0 .1521000002830 3103 105 11900000.0 .154500000 12300000.0 .157000000 12600000.0 .1578000002830 3103 106 12700000.0 .157800000 13000000.0 .157000000 13200000.0 .1557000002830 3103 107 13500000.0 .152900000 13800000.0 .149100000 14000000.0 .1460000002830 3103 108 14700000.0 .130400000 15300000.0 .117600000 15800000.0 .1074000002830 3103 109 16100000.0 .101400000 16400000.0 .095320000 16700000.0 .0898700002830 3103 110 17000000.0 .085000000 17300000.0 .080880000 17600000.0 .0772000002830 3103 111 17900000.0 .073970000 18000000.0 .073000000 18500000.0 .0692500002830 3103 112 19000000.0 .066000000 19700000.0 .062600000 20000000.0 .0610000002830 3103 113 2830 3 0 114 2830 0 0 115 0 0 0 116 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0