IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 2.80620E+4 6.14000E+1 0 0 1 12838 1451 1 0.0 0.0 0 0 0 02838 1451 2 0.0 0.0 0 0 84 32838 1451 3 28-Ni- 62 1USALRL EVAL- 76 2838 1451 4 2838 1451 5 IDENTIFIER=ENDL 2838 2838 1451 6 FORMAT= ENDF/B-5 2838 1451 7 =============================================================== 2838 1451 8 ======================== For MF = 103 ======================= 2838 1451 9 2838 1451 10 HISTORY= 840315 DATA WERE CONVERTED IN ENDF/B-5 FORMAT BY NDS 2838 1451 11 TEXT= 28-NI-62(N,P)27-CO-62-G 2838 1451 12 THIS EVALUATED CROSS-SECTION WAS TAKEN FROM LIVERMORE ACTIVATION 2838 1451 13 LIBRARY 2838 1451 14 ================================================================= 2838 1451 15 Excitation of metastable product cannot be stored in ENDF-5 format2838 1451 16 2838 1451 17 TEXT= 28-NI-62(N,P)27-CO-62-M 2838 1451 18 THIS EVALUATED CROSS-SECTION WAS TAKEN FROM LIVERMORE ACTIVATION 2838 1451 19 LIBRARY 2838 1451 20 2838 1451 21 2838 1451 22 0.28062E 05 0.6140E 02 0 1 0 02838 1451 23 0.29300E 03-0.4484E 07 0 0 1 132838 1451 24 13 2 2838 1451 25 0.6525E 07 0.0 0.7000E 07 0.2500E-03 0.8000E 07 0.1500E-022838 1451 26 0.9000E 07 0.4000E-02 0.1000E 08 0.7000E-02 0.1100E 08 0.1000E-012838 1451 27 0.1200E 08 0.1300E-01 0.1300E 08 0.1600E-01 0.1400E 08 0.2000E-012838 1451 28 0.1500E 08 0.2400E-01 0.1600E 08 0.2500E-01 0.1800E 08 0.1800E-012838 1451 29 0.2000E 08 0.1100E-01 0.0 0.0 0.0 0.0 2838 1451 30 ================================================================= 2838 1451 31 2838 1451 32 =============================================================== 2838 1451 33 ======================== For MF = 107 ======================= 2838 1451 34 2838 1451 35 2.80620+ 4 6.13964+ 1 0 0 1 12838 1451 36 0.0 + 0 0.0 + 0 0 0 0 02838 1451 37 0.0 + 0 0.0 + 0 0 0 30 22838 1451 38 28-Ni-62 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.2838 1451 39 YK-3,(42),60 ,8109 DIST-JAN81 820212 2838 1451 40 IDENTIFIER=INDL 2840 REV1 2838 1451 41 FORMAT= ENDF/B-5 2838 1451 42 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 2838 1451 43 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 2838 1451 44 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 2838 1451 45 TEXT= 2838 1451 46 28-NI-62(N,A)26-FE-59 EN.REG. UP TO 20.MEV IN STEPS OF 100.KEV 2838 1451 47 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 2838 1451 48 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 2838 1451 49 OBNINSK,USSR). 2838 1451 50 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 2838 1451 51 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 2838 1451 52 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 2838 1451 53 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 2838 1451 54 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 2838 1451 55 KONSTANTY,32(1),PAGE 105,1979 2838 1451 56 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 2838 1451 57 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 2838 1451 58 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 2838 1451 59 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 2838 1451 60 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 2838 1451 61 YAD. KOSTANTY 3,(42),P.60,(1981) 2838 1451 62 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.2838 1451 63 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 2838 1451 64 REACTION | V.2,P.271,IAEA,VIENNA) 2838 1451 65 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 2838 1451 66 -------------|-------------|---------------|------------------ 2838 1451 67 28-NI-62(N,A) | 0.0289 | 0.0255 | 0.0327 2838 1451 68 =============================================================== 2838 1451 69 ***************** Program LINEAR (VERSION 2002-1) ***************2838 1451 70 For All Data Greater than 1.0000E-10 barns in Absolute Value 2838 1451 71 Data Linearized to Within an Accuracy of .100000000 per-cent 2838 1451 72 ***************** Program FIXUP (Version 2002-1) ****************2838 1451 73 Corrected ZA/AWR in All Sections-----------------------------Yes 2838 1451 74 Corrected Thresholds-----------------------------------------Yes 2838 1451 75 Extended Cross Sections to 20 MeV----------------------------No 2838 1451 76 Allow Cross Section Deletion---------------------------------No 2838 1451 77 Allow Cross Section Reconstruction---------------------------No 2838 1451 78 Make All Cross Sections Non-Negative-------------------------Yes 2838 1451 79 Delete Energies Not in Ascending Order-----------------------Yes 2838 1451 80 Deleted Duplicate Points-------------------------------------Yes 2838 1451 81 Check for Ascending MAT/MF/MT Order--------------------------Yes 2838 1451 82 Check for Legal MF/MT Numbers--------------------------------Yes 2838 1451 83 Allow Creation of Missing Sections---------------------------No 2838 1451 84 Allow Insertion of Energy Points-----------------------------No 2838 1451 85 Create Uniform Energy Grid-----------------------------------No 2838 1451 86 Delete Section if Cross Section =0 at All Energies-----------Yes 2838 1451 87 1 451 90 12838 1451 88 3 103 6 12838 1451 89 3 107 10 12838 1451 90 2838 1 0 91 2838 0 0 92 2.80620E+4 6.14000E+1 0 0 0 02838 3103 93 2.93000E+2-4.45900E+6 0 0 1 92838 3103 94 9 2 2838 3103 95 4531622.15 0.0 6500000.00 0.0 7000000.00 .0002500002838 3103 96 8000000.00 .001500000 9000000.00 .004000000 13000000.0 .0160000002838 3103 97 15000000.0 .024000000 16000000.0 .025000000 20000000.0 .0110000002838 3103 98 2838 3 0 99 2.80620E+4 6.14000E+1 0 0 0 02838 3107 100 2.93000E+2-4.30000E+5 0 0 1 202838 3107 101 20 2 2838 3107 102 437003.257 0.0 4400000.00 0.0 8000000.00 0.0 2838 3107 103 10000000.0 .008000000 10200000.0 .008880000 10500000.0 .0101300002838 3107 104 10800000.0 .011280000 11000000.0 .012000000 12000000.0 .0150000002838 3107 105 12300000.0 .016000000 12500000.0 .016630000 12800000.0 .0174800002838 3107 106 13000000.0 .018000000 14000000.0 .020000000 14200000.0 .0206400002838 3107 107 14400000.0 .021160000 14600000.0 .021560000 14800000.0 .0218400002838 3107 108 15000000.0 .022000000 20000000.0 .017000000 2838 3107 109 2838 3 0 110 2838 0 0 111 0 0 0 112 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0