IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 9.22380E+4 2.36006E+2 0 0 1 19230 1451 1 0.0 0.0 0 0 0 09230 1451 2 0.0 0.0 0 0 48 29230 1451 3 92-U -238 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.9230 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 9230 1451 5 IDENTIFIER=INDL 9230 REV1 9230 1451 6 FORMAT= ENDF/B-5 9230 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 9230 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 9230 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 9230 1451 10 TEXT= 9230 1451 11 92-U-238(N,2N)92-U-237 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 9230 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 9230 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 9230 1451 14 OBNINSK,USSR). 9230 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 9230 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 9230 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 9230 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 9230 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 9230 1451 20 KONSTANTY,32(1),PAGE 105,1979 9230 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 9230 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 9230 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 9230 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 9230 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 9230 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 9230 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.9230 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 9230 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 9230 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 9230 1451 31 -------------|-------------|---------------|------------------ 9230 1451 32 92-U-238(N,2N) | 14.5 | 13.4 | 14.8 9230 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************9230 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 9230 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 9230 1451 36 ***************** Program FIXUP (Version 2002-1) ****************9230 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 9230 1451 38 Corrected Thresholds-----------------------------------------Yes 9230 1451 39 Extended Cross Sections to 20 MeV----------------------------No 9230 1451 40 Allow Cross Section Deletion---------------------------------No 9230 1451 41 Allow Cross Section Reconstruction---------------------------No 9230 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 9230 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 9230 1451 44 Deleted Duplicate Points-------------------------------------Yes 9230 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 9230 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 9230 1451 47 Allow Creation of Missing Sections---------------------------No 9230 1451 48 Allow Insertion of Energy Points-----------------------------No 9230 1451 49 Create Uniform Energy Grid-----------------------------------No 9230 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 9230 1451 51 1 451 53 19230 1451 52 3 16 23 19230 1451 53 9230 1 0 54 9230 0 0 55 9.22380E+4 2.36006E+2 0 1 0 09230 3 16 56 2.93000E+2-6.14000E+6 0 0 1 599230 3 16 57 59 2 9230 3 16 58 6166016.29 0.0 6200000.00 0.0 6300000.00 .0100000009230 3 16 59 6400000.00 .040000000 6500000.00 .100000000 6700000.00 .2000000009230 3 16 60 7000000.00 .500000000 7100000.00 .571800000 7200000.00 .6404000009230 3 16 61 7300000.00 .705600000 7400000.00 .767600000 7500000.00 .8262000009230 3 16 62 7600000.00 .881600000 7700000.00 .933600000 7800000.00 .9824000009230 3 16 63 7900000.00 1.02800000 8000000.00 1.07000000 8200000.00 1.130000009230 3 16 64 8400000.00 1.18400000 8600000.00 1.23200000 8800000.00 1.274000009230 3 16 65 9000000.00 1.31000000 9300000.00 1.34400000 9600000.00 1.372000009230 3 16 66 9900000.00 1.39400000 10200000.0 1.40800000 10600000.0 1.418000009230 3 16 67 11100000.0 1.42200000 11300000.0 1.42400000 11600000.0 1.416000009230 3 16 68 11800000.0 1.40600000 12200000.0 1.37400000 12400000.0 1.350000009230 3 16 69 12600000.0 1.32000000 12800000.0 1.28400000 13000000.0 1.240000009230 3 16 70 14000000.0 .920000000 14200000.0 .845200000 14400000.0 .7768000009230 3 16 71 14500000.0 .745000000 14600000.0 .714800000 14700000.0 .6862000009230 3 16 72 14800000.0 .659200000 14900000.0 .633800000 15000000.0 .6100000009230 3 16 73 15300000.0 .559700000 15500000.0 .528700000 15700000.0 .4997000009230 3 16 74 15900000.0 .472700000 16000000.0 .460000000 16300000.0 .4268000009230 3 16 75 16600000.0 .396400000 16900000.0 .368600000 17200000.0 .3436000009230 3 16 76 17500000.0 .321200000 17700000.0 .307800000 17900000.0 .2956000009230 3 16 77 18000000.0 .290000000 20000000.0 .210000000 9230 3 16 78 9230 3 0 79 9230 0 0 80 0 0 0 81 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0