IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 2.20500E+4 4.90696E+1 0 0 1 12270 1451 1 0.0 0.0 0 0 0 02270 1451 2 0.0 0.0 0 0 66 32270 1451 3 22-Ti- 50 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.2270 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 2270 1451 5 IDENTIFIER=INDL 2270 REV1 2270 1451 6 FORMAT= ENDF/B-5 2270 1451 7 ======================= For MF = 103 ======================== 2270 1451 8 2270 1451 9 =============================================================== 2270 1451 10 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 2270 1451 11 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 2270 1451 12 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 2270 1451 13 TEXT= 2270 1451 14 22-TI-50(N,P)21-SC-50 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 2270 1451 15 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 2270 1451 16 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 2270 1451 17 OBNINSK,USSR). 2270 1451 18 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 2270 1451 19 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 2270 1451 20 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 2270 1451 21 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 2270 1451 22 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 2270 1451 23 KONSTANTY,32(1),PAGE 105,1979 2270 1451 24 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 2270 1451 25 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 2270 1451 26 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 2270 1451 27 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 2270 1451 28 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 2270 1451 29 YAD. KOSTANTY 3,(42),P.60,(1981) 2270 1451 30 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.2270 1451 31 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 2270 1451 32 REACTION | V.2,P.271,IAEA,VIENNA) 2270 1451 33 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 2270 1451 34 -------------|-------------|---------------|------------------ 2270 1451 35 22-TI-50(N,P) | 0.0085 | 0.0073 | 0.01 2270 1451 36 ======================= For MF = 107 ======================== 2270 1451 37 2270 1451 38 0.22050E 05 0.4952E 02 0 0 1 12270 1451 39 0.0 0.0 0 0 0 02270 1451 40 0.0 0.0 0 0 9 22270 1451 41 22-Ti- 50 1USALRL EVAL- 76 2270 1451 42 2270 1451 43 IDENTIFIER=ENDL 2236 2270 1451 44 FORMAT= ENDF/B-5 2270 1451 45 HISTORY= 840315 DATA WERE CONVERTED IN ENDF/B-5 FORMAT BY NDS 2270 1451 46 2270 1451 47 TEXT= 2270 1451 48 THIS EVALUATED CROSS-SECTION WAS TAKEN FROM LIVERMORE ACTIVATION 2270 1451 49 LIBRARY 2270 1451 50 =============================================================== 2270 1451 51 ***************** Program LINEAR (VERSION 2002-1) ***************2270 1451 52 For All Data Greater than 1.0000E-10 barns in Absolute Value 2270 1451 53 Data Linearized to Within an Accuracy of .100000000 per-cent 2270 1451 54 ***************** Program FIXUP (Version 2002-1) ****************2270 1451 55 Corrected ZA/AWR in All Sections-----------------------------Yes 2270 1451 56 Corrected Thresholds-----------------------------------------Yes 2270 1451 57 Extended Cross Sections to 20 MeV----------------------------No 2270 1451 58 Allow Cross Section Deletion---------------------------------No 2270 1451 59 Allow Cross Section Reconstruction---------------------------No 2270 1451 60 Make All Cross Sections Non-Negative-------------------------Yes 2270 1451 61 Delete Energies Not in Ascending Order-----------------------Yes 2270 1451 62 Deleted Duplicate Points-------------------------------------Yes 2270 1451 63 Check for Ascending MAT/MF/MT Order--------------------------Yes 2270 1451 64 Check for Legal MF/MT Numbers--------------------------------Yes 2270 1451 65 Allow Creation of Missing Sections---------------------------No 2270 1451 66 Allow Insertion of Energy Points-----------------------------No 2270 1451 67 Create Uniform Energy Grid-----------------------------------No 2270 1451 68 Delete Section if Cross Section =0 at All Energies-----------Yes 2270 1451 69 1 451 72 12270 1451 70 3 103 25 12270 1451 71 3 107 9 12270 1451 72 2270 1 0 73 2270 0 0 74 2.20500E+4 4.90696E+1 0 0 0 02270 3103 75 2.93000E+2-6.11000E+6 0 0 1 662270 3103 76 66 2 2270 3103 77 6234517.01 0.0 8000000.00 0.0 8100000.00 2.40000E-52270 3103 78 8200000.00 5.60000E-5 8300000.00 9.60000E-5 8400000.00 .0001440002270 3103 79 8500000.00 .000200000 8600000.00 .000264000 8700000.00 .0003360002270 3103 80 8800000.00 .000416000 8900000.00 .000504000 9000000.00 .0006000002270 3103 81 9100000.00 .000713000 9200000.00 .000832000 9300000.00 .0009570002270 3103 82 9400000.00 .001088000 9500000.00 .001225000 9600000.00 .0013680002270 3103 83 9700000.00 .001517000 9800000.00 .001672000 9900000.00 .0018330002270 3103 84 10100000.0 .002164000 10200000.0 .002336000 10300000.0 .0025160002270 3103 85 10400000.0 .002704000 10500000.0 .002900000 10600000.0 .0031040002270 3103 86 10700000.0 .003316000 10800000.0 .003536000 10900000.0 .0037640002270 3103 87 11000000.0 .004000000 11200000.0 .004512000 11400000.0 .0050480002270 3103 88 11600000.0 .005608000 11800000.0 .006192000 12200000.0 .0074160002270 3103 89 12400000.0 .008064000 12700000.0 .009096000 13000000.0 .0102000002270 3103 90 13500000.0 .012350000 14000000.0 .014400000 14100000.0 .0149000002270 3103 91 14300000.0 .015810000 14500000.0 .016630000 14700000.0 .0173300002270 3103 92 14900000.0 .017940000 15000000.0 .018200000 15200000.0 .0186000002270 3103 93 15400000.0 .018920000 15600000.0 .019160000 15800000.0 .0193200002270 3103 94 16000000.0 .019400000 16100000.0 .019400000 16400000.0 .0193000002270 3103 95 16600000.0 .019140000 16900000.0 .018760000 17000000.0 .0186000002270 3103 96 17600000.0 .017090000 18100000.0 .015720000 18600000.0 .0142500002270 3103 97 19000000.0 .013000000 19200000.0 .012260000 19400000.0 .0115400002270 3103 98 19600000.0 .010860000 19900000.0 .009904000 20000000.0 .0096000002270 3103 99 2270 3 0 100 2.20500E+4 4.90696E+1 0 0 0 02270 3107 101 2.93000E+2-3.44200E+6 0 0 1 182270 3107 102 18 2 2270 3107 103 3512145.26 0.0 10650000.0 0.0 10950000.0 .0001119002270 3107 104 11250000.0 .000440000 11550000.0 .000962900 11850000.0 .0016470002270 3107 105 12150000.0 .002452000 13050000.0 .005132000 13650000.0 .0067530002270 3107 106 14250000.0 .008021000 14550000.0 .008506000 15150000.0 .0092040002270 3107 107 16050000.0 .009739000 18150000.0 .009998000 18450000.0 .0099200002270 3107 108 19050000.0 .009431000 19950000.0 .008089000 20000000.0 .0080890002270 3107 109 2270 3 0 110 2270 0 0 111 0 0 0 112 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0