IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 4.00940E+4 9.31000E+1 0 0 1 14036 1451 1 0.0 0.0 0 0 0 04036 1451 2 0.0 0.0 0 0 67 34036 1451 3 40-Zr- 94 1USALRL EVAL- 76 4036 1451 4 4036 1451 5 IDENTIFIER=ENDL 4036 4036 1451 6 FORMAT= ENDF/B-5 4036 1451 7 =============================================================== 4036 1451 8 ========================= For MF = 103 ======================= 4036 1451 9 4036 1451 10 HISTORY= 840315 DATA WERE CONVERTED IN ENDF/B-5 FORMAT BY NDS 4036 1451 11 4036 1451 12 TEXT= 40-ZR-94(N,P)39-Y-94 T(1/2)=1.2180E+03 SEC 4036 1451 13 THIS EVALUATED CROSS-SECTION WAS TAKEN FROM LIVERMORE ACTIVATION 4036 1451 14 LIBRARY 4036 1451 15 =============================================================== 4036 1451 16 ========================= For MF = 107 ======================= 4036 1451 17 4.00940+ 4 9.30996+ 1 0 0 1 14036 1451 18 0.0 + 0 0.0 + 0 0 0 0 04036 1451 19 0.0 + 0 0.0 + 0 0 0 30 24036 1451 20 40-Zr- 94 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.4036 1451 21 YK-3,(42),60 ,8109 DIST-JAN81 820212 4036 1451 22 IDENTIFIER=INDL 4070 REV1 4036 1451 23 FORMAT= ENDF/B-5 4036 1451 24 HISTORY= 4036 1451 25 840220 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 4036 1451 26 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 4036 1451 27 TEXT= 4036 1451 28 40-ZR-94(N,A)38-SR-91 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 4036 1451 29 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 4036 1451 30 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 4036 1451 31 OBNINSK,USSR). 4036 1451 32 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 4036 1451 33 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 4036 1451 34 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 4036 1451 35 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 4036 1451 36 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 4036 1451 37 KONSTANTY,32(1),PAGE 105,1979 4036 1451 38 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 4036 1451 39 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 4036 1451 40 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 4036 1451 41 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 4036 1451 42 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 4036 1451 43 YAD. KOSTANTY 3,(42),P.60,(1981) 4036 1451 44 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.4036 1451 45 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 4036 1451 46 REACTION | V.2,P.271,IAEA,VIENNA) 4036 1451 47 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 4036 1451 48 -------------|-------------|---------------|------------------ 4036 1451 49 40-ZR-94(N,A) | 0.015 | | 4036 1451 50 4036 1451 51 =============================================================== 4036 1451 52 ***************** Program LINEAR (VERSION 2002-1) ***************4036 1451 53 For All Data Greater than 1.0000E-10 barns in Absolute Value 4036 1451 54 Data Linearized to Within an Accuracy of .100000000 per-cent 4036 1451 55 ***************** Program FIXUP (Version 2002-1) ****************4036 1451 56 Corrected ZA/AWR in All Sections-----------------------------Yes 4036 1451 57 Corrected Thresholds-----------------------------------------Yes 4036 1451 58 Extended Cross Sections to 20 MeV----------------------------No 4036 1451 59 Allow Cross Section Deletion---------------------------------No 4036 1451 60 Allow Cross Section Reconstruction---------------------------No 4036 1451 61 Make All Cross Sections Non-Negative-------------------------Yes 4036 1451 62 Delete Energies Not in Ascending Order-----------------------Yes 4036 1451 63 Deleted Duplicate Points-------------------------------------Yes 4036 1451 64 Check for Ascending MAT/MF/MT Order--------------------------Yes 4036 1451 65 Check for Legal MF/MT Numbers--------------------------------Yes 4036 1451 66 Allow Creation of Missing Sections---------------------------No 4036 1451 67 Allow Insertion of Energy Points-----------------------------No 4036 1451 68 Create Uniform Energy Grid-----------------------------------No 4036 1451 69 Delete Section if Cross Section =0 at All Energies-----------Yes 4036 1451 70 1 451 73 14036 1451 71 3 103 9 14036 1451 72 3 107 7 14036 1451 73 4036 1 0 74 4036 0 0 75 4.00940E+4 9.31000E+1 0 0 0 04036 3103 76 2.93000E+2-4.10000E+6 0 0 1 184036 3103 77 18 2 4036 3103 78 4144038.67 0.0 9873000.00 0.0 10170000.0 .0001303004036 3103 79 10470000.0 .000511300 10770000.0 .001115000 11070000.0 .0018970004036 3103 80 11370000.0 .002804000 12270000.0 .005720000 12570000.0 .0066000004036 3103 81 12870000.0 .007380000 13170000.0 .008048000 13470000.0 .0085990004036 3103 82 13770000.0 .009039000 14070000.0 .009379000 14670000.0 .0098210004036 3103 83 15570000.0 .010100000 16770000.0 .010190000 20000000.0 .0102000004036 3103 84 4036 3 0 85 4.00940E+4 9.31000E+1 0 1 0 04036 3107 86 2.93000E+2 2.06700E+6 0 0 1 124036 3107 87 12 2 4036 3107 88 100000.000 0.0 9000000.00 0.0 9500000.00 .0002000004036 3107 89 10000000.0 .000500000 12000000.0 .002100000 13000000.0 .0030000004036 3107 90 15000000.0 .005000000 16000000.0 .005500000 17000000.0 .0053000004036 3107 91 18000000.0 .004400000 19000000.0 .003400000 20000000.0 .0026000004036 3107 92 4036 3 0 93 4036 0 0 94 0 0 0 95 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0