IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 4.71090E+4 1.07969E+2 0 0 1 14730 1451 1 0.0 0.0 0 0 0 04730 1451 2 0.0 0.0 0 0 67 34730 1451 3 47-Ag-109 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.4730 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 4730 1451 5 IDENTIFIER=INDL 4530 REV1 4730 1451 6 FORMAT= ENDF/B-5 4730 1451 7 =============================================================== 4730 1451 8 ========================= For MF = 103 ======================= 4730 1451 9 4730 1451 10 HISTORY= 4730 1451 11 840220 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 4730 1451 12 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 4730 1451 13 TEXT= 4730 1451 14 47-AG-109(N,P)46-PD-109 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 4730 1451 15 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 4730 1451 16 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 4730 1451 17 OBNINSK,USSR). 4730 1451 18 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 4730 1451 19 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 4730 1451 20 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 4730 1451 21 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 4730 1451 22 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 4730 1451 23 KONSTANTY,32(1),PAGE 105,1979 4730 1451 24 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 4730 1451 25 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 4730 1451 26 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 4730 1451 27 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 4730 1451 28 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 4730 1451 29 YAD. KOSTANTY 3,(42),P.60,(1981) 4730 1451 30 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.4730 1451 31 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 4730 1451 32 REACTION | V.2,P.271,IAEA,VIENNA) 4730 1451 33 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 4730 1451 34 -------------|-------------|---------------|------------------ 4730 1451 35 47-AG-109(N,P) | 0.095 | | 4730 1451 36 =============================================================== 4730 1451 37 ========================= For MF = 107 ======================= 4730 1451 38 0.47109E 05 0.1080E 03 0 0 1 14730 1451 39 0.0 0.0 0 0 0 04730 1451 40 0.0 0.0 0 0 9 24730 1451 41 47-Ag-109 1USALRL EVAL- 73 4730 1451 42 4730 1451 43 IDENTIFIER=ENDL 4736 4730 1451 44 FORMAT= ENDF/B-5 4730 1451 45 HISTORY= 840315 DATA WERE CONVERTED IN ENDF/B-5 FORMAT BY NDS 4730 1451 46 4730 1451 47 TEXT= 4730 1451 48 THIS EVALUATED CROSS-SECTION WAS TAKEN FROM LIVERMORE ACTIVATION 4730 1451 49 LIBRARY 4730 1451 50 4730 1451 51 =============================================================== 4730 1451 52 ***************** Program LINEAR (VERSION 2002-1) ***************4730 1451 53 For All Data Greater than 1.0000E-10 barns in Absolute Value 4730 1451 54 Data Linearized to Within an Accuracy of .100000000 per-cent 4730 1451 55 ***************** Program FIXUP (Version 2002-1) ****************4730 1451 56 Corrected ZA/AWR in All Sections-----------------------------Yes 4730 1451 57 Corrected Thresholds-----------------------------------------Yes 4730 1451 58 Extended Cross Sections to 20 MeV----------------------------No 4730 1451 59 Allow Cross Section Deletion---------------------------------No 4730 1451 60 Allow Cross Section Reconstruction---------------------------No 4730 1451 61 Make All Cross Sections Non-Negative-------------------------Yes 4730 1451 62 Delete Energies Not in Ascending Order-----------------------Yes 4730 1451 63 Deleted Duplicate Points-------------------------------------Yes 4730 1451 64 Check for Ascending MAT/MF/MT Order--------------------------Yes 4730 1451 65 Check for Legal MF/MT Numbers--------------------------------Yes 4730 1451 66 Allow Creation of Missing Sections---------------------------No 4730 1451 67 Allow Insertion of Energy Points-----------------------------No 4730 1451 68 Create Uniform Energy Grid-----------------------------------No 4730 1451 69 Delete Section if Cross Section =0 at All Energies-----------Yes 4730 1451 70 1 451 73 14730 1451 71 3 103 8 14730 1451 72 3 107 7 14730 1451 73 4730 1 0 74 4730 0 0 75 4.71090E+4 1.07969E+2 0 1 0 04730 3103 76 2.93000E+2-3.33000E+5 0 0 1 134730 3103 77 13 2 4730 3103 78 336100.000 0.0 6700000.00 0.0 7500000.00 .0006000004730 3103 79 8000000.00 .001000000 9000000.00 .002200000 10000000.0 .0040000004730 3103 80 12000000.0 .008000000 13000000.0 .011000000 15000000.0 .0150000004730 3103 81 17000000.0 .015800000 18000000.0 .015900000 19000000.0 .0156000004730 3103 82 20000000.0 .015000000 4730 3103 83 4730 3 0 84 4.71090E+4 1.07969E+2 0 0 0 04730 3107 85 2.93000E+2 3.29700E+6 0 0 1 124730 3107 86 12 2 4730 3107 87 5500000.00 0.0 9000000.00 .003940000 9701000.00 .0043120004730 3107 88 10160000.0 .004580000 10500000.0 .004800000 10610000.0 .0048900004730 3107 89 11210000.0 .005413000 12000000.0 .006380000 12120000.0 .0065630004730 3107 90 13500000.0 .009160000 15000000.0 .012260000 20000000.0 .0150000004730 3107 91 4730 3 0 92 4730 0 0 93 0 0 0 94 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0