IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 9.02320E+4 2.30045E+2 0 0 1 19030 1451 1 0.0 0.0 0 0 0 09030 1451 2 0.0 0.0 0 0 48 29030 1451 3 90-Th-232 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.9030 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 9030 1451 5 IDENTIFIER=INDL 9030 REV1 9030 1451 6 FORMAT= ENDF/B-5 9030 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 9030 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 9030 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 9030 1451 10 TEXT= 9030 1451 11 90-TH-232(N,2N)90-TH-231 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 9030 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 9030 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 9030 1451 14 OBNINSK,USSR). 9030 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 9030 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 9030 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 9030 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 9030 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 9030 1451 20 KONSTANTY,32(1),PAGE 105,1979 9030 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 9030 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 9030 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 9030 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 9030 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 9030 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 9030 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.9030 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 9030 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 9030 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 9030 1451 31 -------------|-------------|---------------|------------------ 9030 1451 32 90-TH-232(N,2N) | 15.4 | 14.1 | 15.9 9030 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************9030 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 9030 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 9030 1451 36 ***************** Program FIXUP (Version 2002-1) ****************9030 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 9030 1451 38 Corrected Thresholds-----------------------------------------Yes 9030 1451 39 Extended Cross Sections to 20 MeV----------------------------No 9030 1451 40 Allow Cross Section Deletion---------------------------------No 9030 1451 41 Allow Cross Section Reconstruction---------------------------No 9030 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 9030 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 9030 1451 44 Deleted Duplicate Points-------------------------------------Yes 9030 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 9030 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 9030 1451 47 Allow Creation of Missing Sections---------------------------No 9030 1451 48 Allow Insertion of Energy Points-----------------------------No 9030 1451 49 Create Uniform Energy Grid-----------------------------------No 9030 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 9030 1451 51 1 451 53 19030 1451 52 3 16 24 19030 1451 53 9030 1 0 54 9030 0 0 55 9.02320E+4 2.30045E+2 0 1 0 09030 3 16 56 2.93000E+2-6.43000E+6 0 0 1 639030 3 16 57 63 2 9030 3 16 58 6457951.05 0.0 6550000.00 0.0 6600000.00 .0500000009030 3 16 59 6700000.00 .110000000 6800000.00 .190000000 6900000.00 .2900000009030 3 16 60 7000000.00 .370000000 7100000.00 .482500000 7200000.00 .5900000009030 3 16 61 7300000.00 .692500000 7400000.00 .790000000 7500000.00 .8825000009030 3 16 62 7600000.00 .970000000 7700000.00 1.05200000 7800000.00 1.130000009030 3 16 63 7900000.00 1.20200000 8000000.00 1.27000000 8100000.00 1.323000009030 3 16 64 8200000.00 1.37300000 8400000.00 1.46500000 8600000.00 1.545000009030 3 16 65 8800000.00 1.61300000 9000000.00 1.67000000 9400000.00 1.725000009030 3 16 66 9700000.00 1.75600000 10000000.0 1.78000000 10600000.0 1.796000009030 3 16 67 11100000.0 1.80300000 11400000.0 1.80700000 11700000.0 1.802000009030 3 16 68 12200000.0 1.78100000 12400000.0 1.76700000 12700000.0 1.735000009030 3 16 69 13000000.0 1.69000000 13300000.0 1.63300000 13600000.0 1.563000009030 3 16 70 13800000.0 1.50900000 14000000.0 1.45000000 15000000.0 1.070000009030 3 16 71 15200000.0 .980000000 15300000.0 .938000000 15400000.0 .8980000009030 3 16 72 15500000.0 .860000000 15600000.0 .824000000 15700000.0 .7900000009030 3 16 73 15800000.0 .758000000 15900000.0 .728000000 16000000.0 .7000000009030 3 16 74 16300000.0 .644800000 16600000.0 .593200000 16900000.0 .5452000009030 3 16 75 17100000.0 .515600000 17400000.0 .474400000 17700000.0 .4358000009030 3 16 76 18000000.0 .400000000 18300000.0 .366800000 18600000.0 .3364000009030 3 16 77 18800000.0 .317600000 19000000.0 .300000000 19300000.0 .2769000009030 3 16 78 19600000.0 .255600000 19900000.0 .236100000 20000000.0 .2300000009030 3 16 79 9030 3 0 80 9030 0 0 81 0 0 0 82 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0