IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 4.81060E+4 1.04997E+2 0 0 1 14830 1451 1 0.0 0.0 0 0 0 04830 1451 2 0.0 0.0 0 0 48 34830 1451 3 48-Cd-106 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.4830 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 4830 1451 5 IDENTIFIER=INDL 4830 REV1 4830 1451 6 FORMAT= ENDF/B-5 4830 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 4830 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 4830 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 4830 1451 10 TEXT= 4830 1451 11 48-CD-106(N,2N)48-CD-105M EN.REG.UP TO 20.MEV IN 100.KEV STEPS 4830 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 4830 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 4830 1451 14 OBNINSK,USSR). 4830 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 4830 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 4830 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 4830 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 4830 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 4830 1451 20 KONSTANTY,32(1),PAGE 105,1979 4830 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 4830 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 4830 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 4830 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 4830 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 4830 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 4830 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.4830 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 4830 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 4830 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 4830 1451 31 -------------|-------------|---------------|------------------ 4830 1451 32 48-CD-106(N,2N)M| 0.132 | 0.108 | 0.182 4830 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************4830 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 4830 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 4830 1451 36 ***************** Program FIXUP (Version 2002-1) ****************4830 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 4830 1451 38 Corrected Thresholds-----------------------------------------Yes 4830 1451 39 Extended Cross Sections to 20 MeV----------------------------No 4830 1451 40 Allow Cross Section Deletion---------------------------------No 4830 1451 41 Allow Cross Section Reconstruction---------------------------No 4830 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 4830 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 4830 1451 44 Deleted Duplicate Points-------------------------------------Yes 4830 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 4830 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 4830 1451 47 Allow Creation of Missing Sections---------------------------No 4830 1451 48 Allow Insertion of Energy Points-----------------------------No 4830 1451 49 Create Uniform Energy Grid-----------------------------------No 4830 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 4830 1451 51 1 451 54 14830 1451 52 3 16 7 14830 1451 53 3 26 13 14830 1451 54 4830 1 0 55 4830 0 0 56 4.81060E+4 1.04997E+2 0 1 0 04830 3 16 57 2.93000E+2-1.09200E+7 0 0 1 124830 3 16 58 12 2 4830 3 16 59 11024003.0 0.0 11100000.0 .010000000 11500000.0 .0207000004830 3 16 60 12000000.0 .456000000 13000000.0 .926000000 14000000.0 1.256000004830 3 16 61 15000000.0 1.40000000 16000000.0 1.48000000 17000000.0 1.528000004830 3 16 62 18000000.0 1.56000000 19000000.0 1.58000000 20000000.0 1.580000004830 3 16 63 4830 3 0 64 4.81060E+4 1.04997E+2 0 1 0 04830 3 26 65 2.93000E+2-1.09200E+7 0 0 1 294830 3 26 66 29 2 4830 3 26 67 11024003.0 0.0 11500000.0 0.0 11600000.0 .0250000004830 3 26 68 11800000.0 .095000000 11900000.0 .120000000 12000000.0 .1600000004830 3 26 69 12200000.0 .222700000 12500000.0 .315000000 12800000.0 .4051000004830 3 26 70 13000000.0 .464000000 13200000.0 .523800000 13500000.0 .6100000004830 3 26 71 13800000.0 .691800000 14000000.0 .744000000 14200000.0 .8006000004830 3 26 72 14400000.0 .852200000 14600000.0 .898600000 14800000.0 .9398000004830 3 26 73 15000000.0 .976000000 15300000.0 1.01600000 15600000.0 1.048000004830 3 26 74 15800000.0 1.06600000 16000000.0 1.08000000 16600000.0 1.097000004830 3 26 75 17100000.0 1.10500000 18600000.0 1.10900000 18800000.0 1.109000004830 3 26 76 19800000.0 1.09900000 20000000.0 1.09600000 4830 3 26 77 4830 3 0 78 4830 0 0 79 0 0 0 80 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0