IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 5.31270E+4 1.25814E+2 0 0 1 25310 1451 1 0.0 0.0 0 0 0 05310 1451 2 0.0 0.0 0 0 48 25310 1451 3 53-I -127 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.5310 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 5310 1451 5 IDENTIFIER=INDL 5310 REV2 5310 1451 6 FORMAT= ENDF/B-5 5310 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 5310 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO ENDF/B-5 5310 1451 9 FORMAT.APPROVED BY AUTHOR. SUPERSEDES BOSPOR-78 LIB=5310,REV1 5310 1451 10 TEXT= 5310 1451 11 53-I-127(N,2N)53-I-126 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 5310 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 5310 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 5310 1451 14 OBNINSK,USSR). 5310 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 5310 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 5310 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 5310 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 5310 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 5310 1451 20 KONSTANTY,32(1),PAGE 105,1979 5310 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 5310 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 5310 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 5310 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 5310 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 5310 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 5310 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.5310 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 5310 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 5310 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 5310 1451 31 -------------|-------------|---------------|------------------ 5310 1451 32 53-I-127(N,2N) | 1.13 | 0.973 | 1.36 5310 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************5310 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 5310 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 5310 1451 36 ***************** Program FIXUP (Version 2002-1) ****************5310 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 5310 1451 38 Corrected Thresholds-----------------------------------------Yes 5310 1451 39 Extended Cross Sections to 20 MeV----------------------------No 5310 1451 40 Allow Cross Section Deletion---------------------------------No 5310 1451 41 Allow Cross Section Reconstruction---------------------------No 5310 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 5310 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 5310 1451 44 Deleted Duplicate Points-------------------------------------Yes 5310 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 5310 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 5310 1451 47 Allow Creation of Missing Sections---------------------------No 5310 1451 48 Allow Insertion of Energy Points-----------------------------No 5310 1451 49 Create Uniform Energy Grid-----------------------------------No 5310 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 5310 1451 51 1 451 53 15310 1451 52 3 16 17 25310 1451 53 5310 1 0 54 5310 0 0 55 5.31270E+4 1.25814E+2 0 1 0 05310 3 16 56 2.93000E+2-9.14000E+6 0 0 1 425310 3 16 57 42 2 5310 3 16 58 9212646.92 0.0 9400000.00 .030000000 9500000.00 .0700000005310 3 16 59 9600000.00 .108000000 9700000.00 .150000000 9900000.00 .2400000005310 3 16 60 10000000.0 .280000000 10100000.0 .346900000 10200000.0 .4116000005310 3 16 61 10300000.0 .474100000 10400000.0 .534400000 10500000.0 .5925000005310 3 16 62 10600000.0 .648400000 10700000.0 .702100000 10800000.0 .7536000005310 3 16 63 10900000.0 .802900000 11000000.0 .850000000 11200000.0 .9312000005310 3 16 64 11400000.0 1.00700000 11600000.0 1.07700000 11800000.0 1.141000005310 3 16 65 12000000.0 1.20000000 12200000.0 1.25000000 12400000.0 1.296000005310 3 16 66 12700000.0 1.35700000 13000000.0 1.41000000 13400000.0 1.461000005310 3 16 67 13700000.0 1.49300000 14100000.0 1.52700000 14500000.0 1.552000005310 3 16 68 14900000.0 1.57100000 15300000.0 1.58100000 16400000.0 1.596000005310 3 16 69 16600000.0 1.59600000 17000000.0 1.59000000 17100000.0 1.591000005310 3 16 70 17400000.0 1.58600000 17700000.0 1.56900000 18000000.0 1.540000005310 3 16 71 18600000.0 1.43000000 19100000.0 1.34300000 20000000.0 1.200000005310 3 16 72 5310 3 0 73 5310 0 0 74 0 0 0 75 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0