IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 5.51330E+4 1.31764E+2 0 0 1 15530 1451 1 0.0 0.0 0 0 0 05530 1451 2 0.0 0.0 0 0 48 25530 1451 3 55-Cs-133 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.5530 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 5530 1451 5 IDENTIFIER=INDL 5530 REV1 5530 1451 6 FORMAT= ENDF/B-5 5530 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 5530 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 5530 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 5530 1451 10 TEXT= 5530 1451 11 55-CS-133(N,2N)55-CS-132 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 5530 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 5530 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 5530 1451 14 OBNINSK,USSR). 5530 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 5530 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 5530 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 5530 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 5530 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 5530 1451 20 KONSTANTY,32(1),PAGE 105,1979 5530 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 5530 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 5530 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 5530 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 5530 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 5530 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 5530 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.5530 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 5530 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 5530 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 5530 1451 31 -------------|-------------|---------------|------------------ 5530 1451 32 55-CS-133(N,2N) | 0.992 | 0.851 | 1.21 5530 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************5530 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 5530 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 5530 1451 36 ***************** Program FIXUP (Version 2002-1) ****************5530 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 5530 1451 38 Corrected Thresholds-----------------------------------------Yes 5530 1451 39 Extended Cross Sections to 20 MeV----------------------------No 5530 1451 40 Allow Cross Section Deletion---------------------------------No 5530 1451 41 Allow Cross Section Reconstruction---------------------------No 5530 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 5530 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 5530 1451 44 Deleted Duplicate Points-------------------------------------Yes 5530 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 5530 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 5530 1451 47 Allow Creation of Missing Sections---------------------------No 5530 1451 48 Allow Insertion of Energy Points-----------------------------No 5530 1451 49 Create Uniform Energy Grid-----------------------------------No 5530 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 5530 1451 51 1 451 53 15530 1451 52 3 16 17 15530 1451 53 5530 1 0 54 5530 0 0 55 5.51330E+4 1.31764E+2 0 1 0 05530 3 16 56 2.93000E+2-8.98000E+6 0 0 1 425530 3 16 57 42 2 5530 3 16 58 9048152.15 0.0 9600000.00 0.0 9800000.00 .1000000005530 3 16 59 9900000.00 .160000000 10000000.0 .210000000 10100000.0 .2713000005530 3 16 60 10200000.0 .331200000 10300000.0 .389700000 10400000.0 .4468000005530 3 16 61 10500000.0 .502500000 10600000.0 .556800000 10700000.0 .6097000005530 3 16 62 10800000.0 .661200000 11000000.0 .760000000 11200000.0 .8524000005530 3 16 63 11400000.0 .939600000 11600000.0 1.02200000 11800000.0 1.098000005530 3 16 64 12000000.0 1.17000000 12200000.0 1.23800000 12400000.0 1.300000005530 3 16 65 12600000.0 1.35600000 12800000.0 1.40600000 13000000.0 1.450000005530 3 16 66 13200000.0 1.48500000 13500000.0 1.52900000 13800000.0 1.563000005530 3 16 67 14000000.0 1.58000000 14300000.0 1.59600000 14600000.0 1.604000005530 3 16 68 14800000.0 1.60400000 15100000.0 1.59600000 15400000.0 1.580000005530 3 16 69 15700000.0 1.55400000 16000000.0 1.52000000 16600000.0 1.416000005530 3 16 70 17000000.0 1.34000000 17400000.0 1.25000000 17800000.0 1.168000005530 3 16 71 18000000.0 1.13000000 19800000.0 .841200000 20000000.0 .8100000005530 3 16 72 5530 3 0 73 5530 0 0 74 0 0 0 75 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0