IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 6.91690E+4 1.67483E+2 0 0 1 16930 1451 1 0.0 0.0 0 0 0 06930 1451 2 0.0 0.0 0 0 48 26930 1451 3 69-Tm-169 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.6930 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 6930 1451 5 IDENTIFIER=INDL 6930 REV1 6930 1451 6 FORMAT= ENDF/B-5 6930 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 6930 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 6930 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 6930 1451 10 TEXT= 6930 1451 11 69-TM-169(N,2N)69-TM-168 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 6930 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 6930 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 6930 1451 14 OBNINSK,USSR). 6930 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 6930 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 6930 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 6930 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 6930 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 6930 1451 20 KONSTANTY,32(1),PAGE 105,1979 6930 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 6930 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 6930 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 6930 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 6930 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 6930 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 6930 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.6930 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 6930 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 6930 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 6930 1451 31 -------------|-------------|---------------|------------------ 6930 1451 32 69-TM-169(N,2N) | 3.56 | 3.14 | 4.03 6930 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************6930 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 6930 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 6930 1451 36 ***************** Program FIXUP (Version 2002-1) ****************6930 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 6930 1451 38 Corrected Thresholds-----------------------------------------Yes 6930 1451 39 Extended Cross Sections to 20 MeV----------------------------No 6930 1451 40 Allow Cross Section Deletion---------------------------------No 6930 1451 41 Allow Cross Section Reconstruction---------------------------No 6930 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 6930 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 6930 1451 44 Deleted Duplicate Points-------------------------------------Yes 6930 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 6930 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 6930 1451 47 Allow Creation of Missing Sections---------------------------No 6930 1451 48 Allow Insertion of Energy Points-----------------------------No 6930 1451 49 Create Uniform Energy Grid-----------------------------------No 6930 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 6930 1451 51 1 451 53 16930 1451 52 3 16 18 16930 1451 53 6930 1 0 54 6930 0 0 55 6.91690E+4 1.67483E+2 0 1 0 06930 3 16 56 2.93000E+2-8.06000E+6 0 0 1 456930 3 16 57 45 2 6930 3 16 58 8108124.29 0.0 8200000.00 .012000000 8300000.00 .0380000006930 3 16 59 8400000.00 .065000000 8500000.00 .105000000 8600000.00 .1500000006930 3 16 60 8700000.00 .200000000 8800000.00 .280000000 8900000.00 .3550000006930 3 16 61 9000000.00 .450000000 9100000.00 .548000000 9200000.00 .6420000006930 3 16 62 9300000.00 .732000000 9400000.00 .818000000 9500000.00 .9000000006930 3 16 63 9600000.00 .978000000 9700000.00 1.05200000 9800000.00 1.122000006930 3 16 64 9900000.00 1.18800000 10000000.0 1.25000000 10200000.0 1.344000006930 3 16 65 10400000.0 1.43200000 10600000.0 1.51200000 10800000.0 1.584000006930 3 16 66 11000000.0 1.65000000 11300000.0 1.72300000 11600000.0 1.790000006930 3 16 67 11900000.0 1.85100000 12300000.0 1.92500000 12600000.0 1.972000006930 3 16 68 12900000.0 2.00900000 13200000.0 2.03600000 13600000.0 2.058000006930 3 16 69 14000000.0 2.07000000 14400000.0 2.07300000 14800000.0 2.061000006930 3 16 70 15300000.0 2.03100000 15700000.0 1.98700000 16000000.0 1.940000006930 3 16 71 16600000.0 1.80000000 17100000.0 1.67300000 18000000.0 1.430000006930 3 16 72 19400000.0 1.06600000 19800000.0 .967600000 20000000.0 .9200000006930 3 16 73 6930 3 0 74 6930 0 0 75 0 0 0 76 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0