IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 2.40520E+4 5.19405E+1 0 0 1 22420 1451 1 0.0 0.0 0 0 0 02420 1451 2 0.0 0.0 0 0 54 32420 1451 3 24-Cr- 52 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.2420 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 2420 1451 5 IDENTIFIER=INDL 2420 REV2 2420 1451 6 FORMAT= ENDF/B-5 2420 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 2420 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 2420 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 2420 1451 10 (N,P) DATA WERE REVISED IN COMP. WITH BOSPOR-78= 2420 1451 11 =2420 REV1. (N,2N) DATA WERE ADDED FOR BOSPOR-80. VP. 2420 1451 12 840427 DATA FOR EN=3.2 - 8.5 MEV WERE REVISED BY VP. 2420 1451 13 2420 1451 14 TEXT= 2420 1451 15 24-CR-52(N,2N)24-CR-51 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 2420 1451 16 24-CR-52(N,P)23-V-52 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 2420 1451 17 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 2420 1451 18 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 2420 1451 19 OBNINSK,USSR). 2420 1451 20 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 2420 1451 21 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 2420 1451 22 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 2420 1451 23 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 2420 1451 24 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 2420 1451 25 KONSTANTY,32(1),PAGE 105,1979 2420 1451 26 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 2420 1451 27 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 2420 1451 28 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 2420 1451 29 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 2420 1451 30 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 2420 1451 31 YAD. KOSTANTY 3,(42),P.60,(1981) 2420 1451 32 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.2420 1451 33 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 2420 1451 34 REACTION | V.2,P.271,IAEA,VIENNA) 2420 1451 35 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 2420 1451 36 -------------|-------------|---------------|------------------ 2420 1451 37 24-CR-52(N,2N)| 0.033 | 0.027 | 0.048 2420 1451 38 24-CR-52(N,P) | 0.76 | 0.71 | 0.78 2420 1451 39 ***************** Program LINEAR (VERSION 2002-1) ***************2420 1451 40 For All Data Greater than 1.0000E-10 barns in Absolute Value 2420 1451 41 Data Linearized to Within an Accuracy of .100000000 per-cent 2420 1451 42 ***************** Program FIXUP (Version 2002-1) ****************2420 1451 43 Corrected ZA/AWR in All Sections-----------------------------Yes 2420 1451 44 Corrected Thresholds-----------------------------------------Yes 2420 1451 45 Extended Cross Sections to 20 MeV----------------------------No 2420 1451 46 Allow Cross Section Deletion---------------------------------No 2420 1451 47 Allow Cross Section Reconstruction---------------------------No 2420 1451 48 Make All Cross Sections Non-Negative-------------------------Yes 2420 1451 49 Delete Energies Not in Ascending Order-----------------------Yes 2420 1451 50 Deleted Duplicate Points-------------------------------------Yes 2420 1451 51 Check for Ascending MAT/MF/MT Order--------------------------Yes 2420 1451 52 Check for Legal MF/MT Numbers--------------------------------Yes 2420 1451 53 Allow Creation of Missing Sections---------------------------No 2420 1451 54 Allow Insertion of Energy Points-----------------------------No 2420 1451 55 Create Uniform Energy Grid-----------------------------------No 2420 1451 56 Delete Section if Cross Section =0 at All Energies-----------Yes 2420 1451 57 1 451 60 12420 1451 58 3 16 17 12420 1451 59 3 103 16 22420 1451 60 2420 1 0 61 2420 0 0 62 2.40520E+4 5.19405E+1 0 0 0 02420 3 16 63 2.93000E+2-1.20400E+7 0 0 1 422420 3 16 64 42 2 2420 3 16 65 12271803.7 0.0 12300000.0 .009375000 12400000.0 .0150000002420 3 16 66 12500000.0 .021880000 12600000.0 .030000000 12700000.0 .0393800002420 3 16 67 12800000.0 .050000000 12900000.0 .061880000 13000000.0 .0750000002420 3 16 68 13100000.0 .097430000 13200000.0 .119300000 13300000.0 .1407000002420 3 16 69 13400000.0 .161500000 13500000.0 .181800000 13600000.0 .2015000002420 3 16 70 13700000.0 .220700000 13800000.0 .239300000 14000000.0 .2750000002420 3 16 71 14100000.0 .292800000 14200000.0 .309800000 14400000.0 .3418000002420 3 16 72 14500000.0 .356800000 14700000.0 .384500000 14800000.0 .3974000002420 3 16 73 15000000.0 .421000000 15200000.0 .440400000 15400000.0 .4576000002420 3 16 74 15600000.0 .472800000 15800000.0 .486000000 16000000.0 .4970000002420 3 16 75 16400000.0 .509100000 16800000.0 .517900000 17200000.0 .5232000002420 3 16 76 17600000.0 .525200000 17700000.0 .525200000 18200000.0 .5226000002420 3 16 77 18600000.0 .516800000 19000000.0 .507000000 19300000.0 .4975000002420 3 16 78 19600000.0 .485400000 19900000.0 .470500000 20000000.0 .4650000002420 3 16 79 2420 3 0 80 2.40520E+4 5.19405E+1 0 0 0 02420 3103 81 2.93000E+2-3.20000E+6 0 0 1 382420 3103 82 38 2 2420 3103 83 3261608.96 0.0 5000000.00 0.0 5100000.00 .0004300002420 3103 84 5500000.00 .005000000 6000000.00 .012000000 6500000.00 .0215000002420 3103 85 7000000.00 .030000000 7500000.00 .035600000 8000000.00 .0410000002420 3103 86 8500000.00 .046000000 9000000.00 .055000000 9400000.00 .0624400002420 3103 87 9900000.00 .071290000 10300000.0 .078320000 10600000.0 .0832000002420 3103 88 10900000.0 .087630000 11200000.0 .091520000 11600000.0 .0960800002420 3103 89 12100000.0 .101100000 12300000.0 .103100000 12500000.0 .1048000002420 3103 90 12900000.0 .106800000 13000000.0 .107000000 13500000.0 .1059000002420 3103 91 14100000.0 .103500000 14500000.0 .101300000 15000000.0 .0980000002420 3103 92 16100000.0 .089110000 16600000.0 .084960000 17300000.0 .0797800002420 3103 93 17600000.0 .077920000 17900000.0 .076420000 18000000.0 .0760000002420 3103 94 19000000.0 .074000000 19100000.0 .074020000 19400000.0 .0738000002420 3103 95 19700000.0 .073130000 20000000.0 .072000000 2420 3103 96 2420 3 0 97 2420 0 0 98 0 0 0 99 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0