IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 2.00420E+4 4.15982E+1 0 0 1 12030 1451 1 0.0 0.0 0 0 0 02030 1451 2 0.0 0.0 0 0 66 32030 1451 3 20-Ca- 42 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.2030 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 2030 1451 5 IDENTIFIER=INDL 2030 REV1 2030 1451 6 FORMAT= ENDF/B-5 2030 1451 7 ======================= For MF = 103 ======================== 2030 1451 8 2030 1451 9 =============================================================== 2030 1451 10 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 2030 1451 11 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 2030 1451 12 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 2030 1451 13 TEXT= 2030 1451 14 10-CA-42(N,P)19-K-42 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 2030 1451 15 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 2030 1451 16 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 2030 1451 17 OBNINSK,USSR). 2030 1451 18 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 2030 1451 19 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 2030 1451 20 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 2030 1451 21 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 2030 1451 22 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 2030 1451 23 KONSTANTY,32(1),PAGE 105,1979 2030 1451 24 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 2030 1451 25 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 2030 1451 26 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 2030 1451 27 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 2030 1451 28 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 2030 1451 29 YAD. KOSTANTY 3,(42),P.60,(1981) 2030 1451 30 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.2030 1451 31 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 2030 1451 32 REACTION | V.2,P.271,IAEA,VIENNA) 2030 1451 33 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 2030 1451 34 -------------|-------------|---------------|------------------ 2030 1451 35 20-CA-42(N,P) | 3.44 | 3.25 | 3.35 2030 1451 36 ======================= For MF = 107 ======================== 2030 1451 37 2030 1451 38 0.20042E 05 0.4160E 02 0 0 1 12030 1451 39 0.0 0.0 0 0 0 02030 1451 40 0.0 0.0 0 0 9 22030 1451 41 20-Ca- 42 1USALRL EVAL- 76 2030 1451 42 2030 1451 43 IDENTIFIER=ENDL 2036 2030 1451 44 FORMAT= ENDF/B-5 2030 1451 45 HISTORY= 840315 DATA WERE CONVERTED IN ENDF/B-5 FORMAT BY NDS 2030 1451 46 2030 1451 47 TEXT= 2030 1451 48 THIS EVALUATED CROSS-SECTION WAS TAKEN FROM LIVERMORE ACTIVATION 2030 1451 49 LIBRARY 2030 1451 50 =============================================================== 2030 1451 51 ***************** Program LINEAR (VERSION 2002-1) ***************2030 1451 52 For All Data Greater than 1.0000E-10 barns in Absolute Value 2030 1451 53 Data Linearized to Within an Accuracy of .100000000 per-cent 2030 1451 54 ***************** Program FIXUP (Version 2002-1) ****************2030 1451 55 Corrected ZA/AWR in All Sections-----------------------------Yes 2030 1451 56 Corrected Thresholds-----------------------------------------Yes 2030 1451 57 Extended Cross Sections to 20 MeV----------------------------No 2030 1451 58 Allow Cross Section Deletion---------------------------------No 2030 1451 59 Allow Cross Section Reconstruction---------------------------No 2030 1451 60 Make All Cross Sections Non-Negative-------------------------Yes 2030 1451 61 Delete Energies Not in Ascending Order-----------------------Yes 2030 1451 62 Deleted Duplicate Points-------------------------------------Yes 2030 1451 63 Check for Ascending MAT/MF/MT Order--------------------------Yes 2030 1451 64 Check for Legal MF/MT Numbers--------------------------------Yes 2030 1451 65 Allow Creation of Missing Sections---------------------------No 2030 1451 66 Allow Insertion of Energy Points-----------------------------No 2030 1451 67 Create Uniform Energy Grid-----------------------------------No 2030 1451 68 Delete Section if Cross Section =0 at All Energies-----------Yes 2030 1451 69 1 451 72 12030 1451 70 3 103 22 12030 1451 71 3 107 5 12030 1451 72 2030 1 0 73 2030 0 0 74 2.00420E+4 4.15982E+1 0 0 0 02030 3103 75 2.93000E+2-2.74000E+6 0 0 1 552030 3103 76 55 2 2030 3103 77 2805868.23 0.0 3900000.00 0.0 4000000.00 .0010000002030 3103 78 4100000.00 .002250000 4200000.00 .003600000 4300000.00 .0050500002030 3103 79 4400000.00 .006600000 4500000.00 .008250000 4600000.00 .0100000002030 3103 80 4700000.00 .011850000 4800000.00 .013800000 4900000.00 .0158500002030 3103 81 5000000.00 .018000000 5100000.00 .020430000 5200000.00 .0229200002030 3103 82 5300000.00 .025470000 5400000.00 .028080000 5600000.00 .0334800002030 3103 83 5800000.00 .039120000 6000000.00 .045000000 6300000.00 .0553200002030 3103 84 6600000.00 .065280000 6900000.00 .074880000 7300000.00 .0873300002030 3103 85 7600000.00 .096120000 7900000.00 .104400000 8300000.00 .1144000002030 3103 86 8700000.00 .123600000 9100000.00 .132000000 9500000.00 .1396000002030 3103 87 9900000.00 .146400000 10300000.0 .152400000 10700000.0 .1576000002030 3103 88 11200000.0 .163200000 11500000.0 .166000000 11900000.0 .1686000002030 3103 89 12300000.0 .169900000 12600000.0 .170100000 13000000.0 .1690000002030 3103 90 13400000.0 .166100000 13900000.0 .161200000 14300000.0 .1559000002030 3103 91 14700000.0 .149900000 15000000.0 .145000000 15600000.0 .1340000002030 3103 92 16100000.0 .123900000 16900000.0 .106300000 17100000.0 .1015000002030 3103 93 17700000.0 .086990000 18300000.0 .073080000 18700000.0 .0642800002030 3103 94 19100000.0 .055960000 19400000.0 .050040000 19700000.0 .0443800002030 3103 95 20000000.0 .039000000 2030 3103 96 2030 3 0 97 2.00420E+4 4.15982E+1 0 0 0 02030 3107 98 2.93000E+2 3.44000E+5 0 0 1 62030 3107 99 6 2 2030 3107 100 5000000.00 0.0 7000000.00 .010000000 8000000.00 .0500000002030 3107 101 9000000.00 .100000000 14000000.0 .120000000 20000000.0 .1200000002030 3107 102 2030 3 0 103 2030 0 0 104 0 0 0 105 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0