IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 5.11230E+4 1.21848E+2 0 0 1 15140 1451 1 0.0 0.0 0 0 0 05140 1451 2 0.0 0.0 0 0 48 25140 1451 3 51-Sb-123 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.5140 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 5140 1451 5 IDENTIFIER=INDL 5140 REV1 5140 1451 6 FORMAT= ENDF/B-5 5140 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 5140 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 5140 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 5140 1451 10 TEXT= 5140 1451 11 51-SB-123(N,2N)51-SB-122 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 5140 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 5140 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 5140 1451 14 OBNINSK,USSR). 5140 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 5140 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 5140 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 5140 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 5140 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 5140 1451 20 KONSTANTY,32(1),PAGE 105,1979 5140 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 5140 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 5140 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 5140 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 5140 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 5140 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 5140 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.5140 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 5140 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 5140 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 5140 1451 31 -------------|-------------|---------------|------------------ 5140 1451 32 51-SB-123(N,2N) | 1.00 | 0.86 | 1.20 5140 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************5140 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 5140 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 5140 1451 36 ***************** Program FIXUP (Version 2002-1) ****************5140 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 5140 1451 38 Corrected Thresholds-----------------------------------------Yes 5140 1451 39 Extended Cross Sections to 20 MeV----------------------------No 5140 1451 40 Allow Cross Section Deletion---------------------------------No 5140 1451 41 Allow Cross Section Reconstruction---------------------------No 5140 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 5140 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 5140 1451 44 Deleted Duplicate Points-------------------------------------Yes 5140 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 5140 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 5140 1451 47 Allow Creation of Missing Sections---------------------------No 5140 1451 48 Allow Insertion of Energy Points-----------------------------No 5140 1451 49 Create Uniform Energy Grid-----------------------------------No 5140 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 5140 1451 51 1 451 53 15140 1451 52 3 16 17 15140 1451 53 5140 1 0 54 5140 0 0 55 5.11230E+4 1.21848E+2 0 1 0 05140 3 16 56 2.93000E+2-8.96000E+6 0 0 1 405140 3 16 57 40 2 5140 3 16 58 9033534.24 0.0 9300000.00 0.0 9400000.00 .0250000005140 3 16 59 9500000.00 .056000000 9600000.00 .104000000 9700000.00 .1480000005140 3 16 60 9800000.00 .195000000 9900000.00 .232000000 10000000.0 .2800000005140 3 16 61 10100000.0 .329400000 10200000.0 .377600000 10300000.0 .4246000005140 3 16 62 10400000.0 .470400000 10500000.0 .515000000 10600000.0 .5584000005140 3 16 63 10800000.0 .641600000 11000000.0 .720000000 11200000.0 .7923000005140 3 16 64 11400000.0 .860500000 11600000.0 .924500000 11900000.0 1.013000005140 3 16 65 12100000.0 1.06600000 12400000.0 1.13700000 12700000.0 1.200000005140 3 16 66 12900000.0 1.23800000 13100000.0 1.27200000 13500000.0 1.328000005140 3 16 67 13900000.0 1.37400000 14200000.0 1.40000000 14700000.0 1.433000005140 3 16 68 15100000.0 1.45200000 15600000.0 1.46600000 16300000.0 1.476000005140 3 16 69 16500000.0 1.47600000 16900000.0 1.46800000 17100000.0 1.458000005140 3 16 70 17700000.0 1.41600000 18200000.0 1.37400000 19200000.0 1.276000005140 3 16 71 20000000.0 1.18800000 5140 3 16 72 5140 3 0 73 5140 0 0 74 0 0 0 75 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0