IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 4.00920E+4 9.11200E+1 0 0 1 14035 1451 1 0.0 0.0 0 0 0 04035 1451 2 0.0 0.0 0 0 67 34035 1451 3 40-Zr- 92 1USALRL EVAL- 76 4035 1451 4 4035 1451 5 IDENTIFIER=ENDL 4035 4035 1451 6 FORMAT= ENDF/B-5 4035 1451 7 =============================================================== 4035 1451 8 ========================= For MF = 103 ======================= 4035 1451 9 4035 1451 10 HISTORY= 840315 DATA WERE CONVERTED IN ENDF/B-5 FORMAT BY NDS 4035 1451 11 4035 1451 12 TEXT= 40-ZR-92(N,P)39-Y-92 T(1/2)=1.2710E+04 SEC 4035 1451 13 THIS EVALUATED CROSS-SECTION WAS TAKEN FROM LIVERMORE ACTIVATION 4035 1451 14 LIBRARY 4035 1451 15 =============================================================== 4035 1451 16 ========================= For MF = 107 ======================= 4035 1451 17 4.00920+ 4 9.11155+ 1 0 0 1 14035 1451 18 0.0 + 0 0.0 + 0 0 0 0 04035 1451 19 0.0 + 0 0.0 + 0 0 0 30 24035 1451 20 40-Zr- 92 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.4035 1451 21 YK-3,(42),60 ,8109 DIST-JAN81 820212 4035 1451 22 IDENTIFIER=INDL 4080 REV1 4035 1451 23 FORMAT= ENDF/B-5 4035 1451 24 HISTORY= 4035 1451 25 840220 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 4035 1451 26 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 4035 1451 27 TEXT= 4035 1451 28 40-ZR-92(N,A)38-SR-89 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 4035 1451 29 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 4035 1451 30 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 4035 1451 31 OBNINSK,USSR). 4035 1451 32 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 4035 1451 33 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 4035 1451 34 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 4035 1451 35 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 4035 1451 36 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 4035 1451 37 KONSTANTY,32(1),PAGE 105,1979 4035 1451 38 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 4035 1451 39 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 4035 1451 40 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 4035 1451 41 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 4035 1451 42 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 4035 1451 43 YAD. KOSTANTY 3,(42),P.60,(1981) 4035 1451 44 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.4035 1451 45 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 4035 1451 46 REACTION | V.2,P.271,IAEA,VIENNA) 4035 1451 47 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 4035 1451 48 -------------|-------------|---------------|------------------ 4035 1451 49 40-ZR-92(N,A) | 0.096 | | 4035 1451 50 4035 1451 51 =============================================================== 4035 1451 52 ***************** Program LINEAR (VERSION 2002-1) ***************4035 1451 53 For All Data Greater than 1.0000E-10 barns in Absolute Value 4035 1451 54 Data Linearized to Within an Accuracy of .100000000 per-cent 4035 1451 55 ***************** Program FIXUP (Version 2002-1) ****************4035 1451 56 Corrected ZA/AWR in All Sections-----------------------------Yes 4035 1451 57 Corrected Thresholds-----------------------------------------Yes 4035 1451 58 Extended Cross Sections to 20 MeV----------------------------No 4035 1451 59 Allow Cross Section Deletion---------------------------------No 4035 1451 60 Allow Cross Section Reconstruction---------------------------No 4035 1451 61 Make All Cross Sections Non-Negative-------------------------Yes 4035 1451 62 Delete Energies Not in Ascending Order-----------------------Yes 4035 1451 63 Deleted Duplicate Points-------------------------------------Yes 4035 1451 64 Check for Ascending MAT/MF/MT Order--------------------------Yes 4035 1451 65 Check for Legal MF/MT Numbers--------------------------------Yes 4035 1451 66 Allow Creation of Missing Sections---------------------------No 4035 1451 67 Allow Insertion of Energy Points-----------------------------No 4035 1451 68 Create Uniform Energy Grid-----------------------------------No 4035 1451 69 Delete Section if Cross Section =0 at All Energies-----------Yes 4035 1451 70 1 451 73 14035 1451 71 3 103 9 14035 1451 72 3 107 7 14035 1451 73 4035 1 0 74 4035 0 0 75 4.00920E+4 9.11200E+1 0 0 0 04035 3103 76 2.93000E+2-2.85200E+6 0 0 1 184035 3103 77 18 2 4035 3103 78 2883299.39 0.0 8512000.00 0.0 8812000.00 .0002371004035 3103 79 9112000.00 .000930600 9412000.00 .002028000 9712000.00 .0034520004035 3103 80 10010000.0 .005103000 10910000.0 .010410000 11210000.0 .0120100004035 3103 81 11510000.0 .013430000 11810000.0 .014650000 12110000.0 .0156500004035 3103 82 12410000.0 .016450000 12710000.0 .017070000 13010000.0 .0175300004035 3103 83 13610000.0 .018110000 14510000.0 .018450000 20000000.0 .0185600004035 3103 84 4035 3 0 85 4.00920E+4 9.11200E+1 0 1 0 04035 3107 86 2.93000E+2 3.38600E+6 0 0 1 124035 3107 87 12 2 4035 3107 88 100000.000 0.0 7000000.00 0.0 8000000.00 .0006000004035 3107 89 9000000.00 .001500000 10000000.0 .002600000 11000000.0 .0040000004035 3107 90 12000000.0 .005000000 13000000.0 .007000000 16000000.0 .0100000004035 3107 91 17000000.0 .010000000 19000000.0 .008000000 20000000.0 .0060000004035 3107 92 4035 3 0 93 4035 0 0 94 0 0 0 95 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0