IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 2.20490E+4 4.85274E+1 0 0 1 12260 1451 1 0.0 0.0 0 0 0 02260 1451 2 0.0 0.0 0 0 48 22260 1451 3 22-Ti- 49 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.2260 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 2260 1451 5 IDENTIFIER=INDL 2260 REV1 2260 1451 6 FORMAT= ENDF/B-5 2260 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 2260 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 2260 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 2260 1451 10 TEXT= 2260 1451 11 22-TI-49(N,P)21-SC-49 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 2260 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 2260 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 2260 1451 14 OBNINSK,USSR). 2260 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 2260 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 2260 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 2260 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 2260 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 2260 1451 20 KONSTANTY,32(1),PAGE 105,1979 2260 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 2260 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 2260 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 2260 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 2260 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 2260 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 2260 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.2260 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 2260 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 2260 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 2260 1451 31 -------------|-------------|---------------|------------------ 2260 1451 32 22-TI-49(N,P) | 0.47 | 0.45 | 0.45 2260 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************2260 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 2260 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 2260 1451 36 ***************** Program FIXUP (Version 2002-1) ****************2260 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 2260 1451 38 Corrected Thresholds-----------------------------------------Yes 2260 1451 39 Extended Cross Sections to 20 MeV----------------------------No 2260 1451 40 Allow Cross Section Deletion---------------------------------No 2260 1451 41 Allow Cross Section Reconstruction---------------------------No 2260 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 2260 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 2260 1451 44 Deleted Duplicate Points-------------------------------------Yes 2260 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 2260 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 2260 1451 47 Allow Creation of Missing Sections---------------------------No 2260 1451 48 Allow Insertion of Energy Points-----------------------------No 2260 1451 49 Create Uniform Energy Grid-----------------------------------No 2260 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 2260 1451 51 1 451 53 12260 1451 52 3 103 16 12260 1451 53 2260 1 0 54 2260 0 0 55 2.20490E+4 4.85274E+1 0 0 0 02260 3103 56 2.93000E+2-1.22000E+6 0 0 1 392260 3103 57 39 2 2260 3103 58 1245140.44 0.0 3300000.00 0.0 3500000.00 .0002000002260 3103 59 3600000.00 .000400000 3900000.00 .000700000 4000000.00 .0010000002260 3103 60 5000000.00 .003000000 5100000.00 .003155000 5200000.00 .0033200002260 3103 61 5300000.00 .003495000 5400000.00 .003680000 5500000.00 .0038750002260 3103 62 5600000.00 .004080000 5700000.00 .004295000 5800000.00 .0045200002260 3103 63 5900000.00 .004755000 6000000.00 .005000000 10000000.0 .0170000002260 3103 64 10500000.0 .018560000 11000000.0 .020000000 11600000.0 .0214400002260 3103 65 12000000.0 .022500000 13000000.0 .025500000 13300000.0 .0265600002260 3103 66 13600000.0 .027480000 13900000.0 .028270000 14300000.0 .0292600002260 3103 67 14500000.0 .029630000 14800000.0 .029940000 15000000.0 .0300000002260 3103 68 15500000.0 .029380000 16000000.0 .028500000 16500000.0 .0273800002260 3103 69 16900000.0 .026290000 17000000.0 .026000000 17400000.0 .0244800002260 3103 70 17800000.0 .023120000 18000000.0 .022500000 20000000.0 .0175000002260 3103 71 2260 3 0 72 2260 0 0 73 0 0 0 74 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0