IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 7.91970E+4 1.95275E+2 0 0 1 17930 1451 1 0.0 0.0 0 0 0 07930 1451 2 0.0 0.0 0 0 71 47930 1451 3 79-Au-197 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.7930 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 7930 1451 5 IDENTIFIER=INDL 7930 REV1 7930 1451 6 FORMAT= ENDF/B-5 7930 1451 7 =============================================================== 7930 1451 8 ======================== For MF = 16 ======================== 7930 1451 9 7930 1451 10 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 7930 1451 11 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 7930 1451 12 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 7930 1451 13 840502 DATA WERE RENORMALIZED BY VP, (K=0.93) 7930 1451 14 TEXT= 7930 1451 15 79-AU-197(N,2N)79-AU-196 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 7930 1451 16 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 7930 1451 17 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 7930 1451 18 OBNINSK,USSR). 7930 1451 19 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 7930 1451 20 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 7930 1451 21 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 7930 1451 22 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 7930 1451 23 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 7930 1451 24 KONSTANTY,32(1),PAGE 105,1979 7930 1451 25 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 7930 1451 26 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 7930 1451 27 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 7930 1451 28 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 7930 1451 29 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 7930 1451 30 YAD. KOSTANTY 3,(42),P.60,(1981) 7930 1451 31 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.7930 1451 32 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 7930 1451 33 REACTION | V.2,P.271,IAEA,VIENNA) 7930 1451 34 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 7930 1451 35 -------------|-------------|---------------|------------------ 7930 1451 36 79-AU-197(N,2N) | 3.23 | 2.84 | 3.69 7930 1451 37 7930 1451 38 =============================================================== 7930 1451 39 ==================== For MF = 26 and 103 ==================== 7930 1451 40 0.79197E 05 0.1953E 03 0 0 1 17930 1451 41 0.0 0.0 0 0 0 07930 1451 42 0.0 0.0 0 0 11 37930 1451 43 79-Au-197 1USALRL EVAL- 76 7930 1451 44 7930 1451 45 IDENTIFIER=ENDL 7935 7930 1451 46 FORMAT= ENDF/B-5 7930 1451 47 HISTORY= 840315 DATA WERE CONVERTED IN ENDF/B-5 FORMAT BY NDS 7930 1451 48 WITH MINOR REVISION 7930 1451 49 TEXT= MT= 26 79-AU-197(N,2N)79-AU-196-M1 T(1/2)=3.4920E+04 SEC 7930 1451 50 THIS EVALUATED CROSS-SECTION WAS TAKEN FROM LIVERMORE ACTIVATION 7930 1451 51 LIBRARY AND MINOR REVISION (SMOOTHING) WAS DONE BY VP,IAEA 7930 1451 52 TEXT= MT=103 7930 1451 53 79-AU-197 1USALRL EVAL- 82 7930 1451 54 7930 1451 55 =============================================================== 7930 1451 56 ***************** Program LINEAR (VERSION 2002-1) ***************7930 1451 57 For All Data Greater than 1.0000E-10 barns in Absolute Value 7930 1451 58 Data Linearized to Within an Accuracy of .100000000 per-cent 7930 1451 59 ***************** Program FIXUP (Version 2002-1) ****************7930 1451 60 Corrected ZA/AWR in All Sections-----------------------------Yes 7930 1451 61 Corrected Thresholds-----------------------------------------Yes 7930 1451 62 Extended Cross Sections to 20 MeV----------------------------No 7930 1451 63 Allow Cross Section Deletion---------------------------------No 7930 1451 64 Allow Cross Section Reconstruction---------------------------No 7930 1451 65 Make All Cross Sections Non-Negative-------------------------Yes 7930 1451 66 Delete Energies Not in Ascending Order-----------------------Yes 7930 1451 67 Deleted Duplicate Points-------------------------------------Yes 7930 1451 68 Check for Ascending MAT/MF/MT Order--------------------------Yes 7930 1451 69 Check for Legal MF/MT Numbers--------------------------------Yes 7930 1451 70 Allow Creation of Missing Sections---------------------------No 7930 1451 71 Allow Insertion of Energy Points-----------------------------No 7930 1451 72 Create Uniform Energy Grid-----------------------------------No 7930 1451 73 Delete Section if Cross Section =0 at All Energies-----------Yes 7930 1451 74 1 451 78 17930 1451 75 3 16 12 17930 1451 76 3 26 6 17930 1451 77 3 103 6 17930 1451 78 7930 1 0 79 7930 0 0 80 7.91970E+4 1.95275E+2 0 1 0 07930 3 16 81 2.93000E+2-8.08000E+6 0 0 1 257930 3 16 82 25 2 7930 3 16 83 8121377.54 0.0 8400000.00 0.0 8500000.00 .0500000007930 3 16 84 9000000.00 .325500000 9500000.00 .700000000 10000000.0 1.023000007930 3 16 85 10500000.0 1.28400000 11000000.0 1.51100000 11500000.0 1.710000007930 3 16 86 12000000.0 1.86000000 12500000.0 1.94400000 13000000.0 2.009000007930 3 16 87 13500000.0 2.05500000 14000000.0 2.08300000 14500000.0 2.096000007930 3 16 88 15000000.0 2.08300000 15500000.0 2.04000000 16000000.0 2.002000007930 3 16 89 16500000.0 1.90600000 17000000.0 1.81400000 18000000.0 1.581000007930 3 16 90 18500000.0 1.46700000 19000000.0 1.34900000 19500000.0 1.224000007930 3 16 91 20000000.0 1.10200000 7930 3 16 92 7930 3 0 93 7.91970E+4 1.95275E+2 0 1 0 07930 3 26 94 2.93000E+2-8.65400E+6 0 0 1 97930 3 26 95 9 2 7930 3 26 96 8698316.99 0.0 9800000.00 .010000000 11000000.0 .0390000007930 3 26 97 12000000.0 .070000000 13000000.0 .100000000 14000000.0 .1260000007930 3 26 98 15000000.0 .140000000 16000000.0 .140000000 20000000.0 .1200000007930 3 26 99 7930 3 0 100 7.91970E+4 1.95275E+2 0 0 0 07930 3103 101 2.93000E+2 6.30000E+4 0 0 1 87930 3103 102 8 2 7930 3103 103 10000000.0 0.0 11800000.0 8.00000E-5 12100000.0 .0007000007930 3103 104 13000000.0 .001000000 14000000.0 .001800000 14600000.0 .0020000007930 3103 105 16000000.0 .006000000 20000000.0 .006000000 7930 3103 106 7930 3 0 107 7930 0 0 108 0 0 0 109 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0