IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 2.20460E+4 4.55579E+1 0 0 1 12230 1451 1 0.0 0.0 0 0 0 02230 1451 2 0.0 0.0 0 0 50 32230 1451 3 22-Ti- 46 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.2230 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 2230 1451 5 IDENTIFIER=INDL 2230 REV1 2230 1451 6 FORMAT= ENDF/B-5 2230 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 2230 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 2230 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 2230 1451 10 TEXT= 2230 1451 11 22-TI-46(N,2N)22-TI-45 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 2230 1451 12 22-TI-46(N,P)21-SC-46 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 2230 1451 13 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 2230 1451 14 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 2230 1451 15 OBNINSK,USSR). 2230 1451 16 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 2230 1451 17 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 2230 1451 18 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 2230 1451 19 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 2230 1451 20 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 2230 1451 21 KONSTANTY,32(1),PAGE 105,1979 2230 1451 22 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 2230 1451 23 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 2230 1451 24 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 2230 1451 25 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 2230 1451 26 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 2230 1451 27 YAD. KOSTANTY 3,(42),P.60,(1981) 2230 1451 28 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.2230 1451 29 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 2230 1451 30 REACTION | V.2,P.271,IAEA,VIENNA) 2230 1451 31 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 2230 1451 32 -------------|-------------|---------------|------------------ 2230 1451 33 22-TI-46(N,2N)| 3.7E-03 | 2.9E-03 | 6.1E-03 2230 1451 34 22-TI-46(N,P) | 12.8 | 12.3 | 12.3 2230 1451 35 ***************** Program LINEAR (VERSION 2002-1) ***************2230 1451 36 For All Data Greater than 1.0000E-10 barns in Absolute Value 2230 1451 37 Data Linearized to Within an Accuracy of .100000000 per-cent 2230 1451 38 ***************** Program FIXUP (Version 2002-1) ****************2230 1451 39 Corrected ZA/AWR in All Sections-----------------------------Yes 2230 1451 40 Corrected Thresholds-----------------------------------------Yes 2230 1451 41 Extended Cross Sections to 20 MeV----------------------------No 2230 1451 42 Allow Cross Section Deletion---------------------------------No 2230 1451 43 Allow Cross Section Reconstruction---------------------------No 2230 1451 44 Make All Cross Sections Non-Negative-------------------------Yes 2230 1451 45 Delete Energies Not in Ascending Order-----------------------Yes 2230 1451 46 Deleted Duplicate Points-------------------------------------Yes 2230 1451 47 Check for Ascending MAT/MF/MT Order--------------------------Yes 2230 1451 48 Check for Legal MF/MT Numbers--------------------------------Yes 2230 1451 49 Allow Creation of Missing Sections---------------------------No 2230 1451 50 Allow Insertion of Energy Points-----------------------------No 2230 1451 51 Create Uniform Energy Grid-----------------------------------No 2230 1451 52 Delete Section if Cross Section =0 at All Energies-----------Yes 2230 1451 53 1 451 56 12230 1451 54 3 16 12 12230 1451 55 3 103 20 12230 1451 56 2230 1 0 57 2230 0 0 58 2.20460E+4 4.55579E+1 0 0 0 02230 3 16 59 2.93000E+2-1.31900E+7 0 0 1 272230 3 16 60 27 2 2230 3 16 61 13480000.0 0.0 13600000.0 .002500000 13900000.0 .0100000002230 3 16 62 14000000.0 .015000000 14100000.0 .019770000 14300000.0 .0294700002230 3 16 63 14500000.0 .039380000 14700000.0 .049470000 15000000.0 .0650000002230 3 16 64 15300000.0 .082020000 15600000.0 .098600000 16200000.0 .1307000002230 3 16 65 16500000.0 .146100000 16800000.0 .160700000 17000000.0 .1700000002230 3 16 66 17200000.0 .179800000 17400000.0 .188800000 17600000.0 .1970000002230 3 16 67 17900000.0 .207800000 18100000.0 .213800000 18400000.0 .2213000002230 3 16 68 18700000.0 .227300000 19100000.0 .233500000 19400000.0 .2367000002230 3 16 69 19700000.0 .238000000 19800000.0 .238000000 20000000.0 .2375000002230 3 16 70 2230 3 0 71 2.20460E+4 4.55579E+1 0 0 0 02230 3103 72 2.93000E+2-1.59000E+6 0 0 1 512230 3103 73 51 2 2230 3103 74 1624900.64 0.0 2900000.00 0.0 3000000.00 .0020000002230 3103 75 3100000.00 .002790000 3200000.00 .003960000 3300000.00 .0055100002230 3103 76 3400000.00 .007440000 3500000.00 .009750000 3600000.00 .0124400002230 3103 77 3700000.00 .015510000 3800000.00 .018960000 3900000.00 .0227900002230 3103 78 4000000.00 .027000000 4200000.00 .039280000 4500000.00 .0580000002230 3103 79 4800000.00 .077080000 5000000.00 .090000000 5100000.00 .0977800002230 3103 80 5200000.00 .105300000 5400000.00 .119700000 5600000.00 .1331000002230 3103 81 5800000.00 .145500000 6000000.00 .157000000 6500000.00 .1791000002230 3103 82 7000000.00 .200000000 7200000.00 .209300000 7500000.00 .2216000002230 3103 83 7800000.00 .232100000 8000000.00 .238000000 9000000.00 .2550000002230 3103 84 9500000.00 .264400000 10000000.0 .272000000 10500000.0 .2780000002230 3103 85 11200000.0 .283500000 11500000.0 .284800000 11700000.0 .2849000002230 3103 86 12000000.0 .284000000 12500000.0 .278900000 13000000.0 .2720000002230 3103 87 13600000.0 .261100000 14200000.0 .248600000 15000000.0 .2300000002230 3103 88 16600000.0 .189800000 17000000.0 .179000000 17600000.0 .1611000002230 3103 89 18000000.0 .150000000 19000000.0 .125000000 19200000.0 .1194000002230 3103 90 19500000.0 .111600000 19800000.0 .104400000 20000000.0 .1000000002230 3103 91 2230 3 0 92 2230 0 0 93 0 0 0 94 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0