IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 4.81120E+4 1.10941E+2 0 0 1 14850 1451 1 0.0 0.0 0 0 0 04850 1451 2 0.0 0.0 0 0 48 24850 1451 3 48-Cd-112 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.4850 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 4850 1451 5 IDENTIFIER=INDL 4850 REV1 4850 1451 6 FORMAT= ENDF/B-5 4850 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 4850 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 4850 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 4850 1451 10 TEXT= 4850 1451 11 48-CD-112(N,A)46-PD-109 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 4850 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 4850 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 4850 1451 14 OBNINSK,USSR). 4850 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 4850 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 4850 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 4850 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 4850 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 4850 1451 20 KONSTANTY,32(1),PAGE 105,1979 4850 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 4850 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 4850 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 4850 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 4850 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 4850 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 4850 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.4850 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 4850 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 4850 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 4850 1451 31 -------------|-------------|---------------|------------------ 4850 1451 32 48-CD-112(N,A) | 0.70E-03 | 0.69E-03 | 0.58E-03 4850 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************4850 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 4850 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 4850 1451 36 ***************** Program FIXUP (Version 2002-1) ****************4850 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 4850 1451 38 Corrected Thresholds-----------------------------------------Yes 4850 1451 39 Extended Cross Sections to 20 MeV----------------------------No 4850 1451 40 Allow Cross Section Deletion---------------------------------No 4850 1451 41 Allow Cross Section Reconstruction---------------------------No 4850 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 4850 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 4850 1451 44 Deleted Duplicate Points-------------------------------------Yes 4850 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 4850 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 4850 1451 47 Allow Creation of Missing Sections---------------------------No 4850 1451 48 Allow Insertion of Energy Points-----------------------------No 4850 1451 49 Create Uniform Energy Grid-----------------------------------No 4850 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 4850 1451 51 1 451 53 14850 1451 52 3 107 20 14850 1451 53 4850 1 0 54 4850 0 0 55 4.81120E+4 1.10941E+2 0 1 0 04850 3107 56 2.93000E+2 0.0 0 0 1 514850 3107 57 51 2 4850 3107 58 1000.00000 0.0 9300000.00 0.0 9500000.00 4.00000E-54850 3107 59 9900000.00 8.00000E-5 10000000.0 .000100000 10100000.0 .0001110004850 3107 60 10200000.0 .000124000 10300000.0 .000139000 10400000.0 .0001560004850 3107 61 10500000.0 .000175000 10600000.0 .000196000 10700000.0 .0002190004850 3107 62 10800000.0 .000244000 10900000.0 .000271000 11000000.0 .0003000004850 3107 63 11100000.0 .000335500 11200000.0 .000372000 11300000.0 .0004095004850 3107 64 11400000.0 .000448000 11500000.0 .000487500 11700000.0 .0005695004850 3107 65 11900000.0 .000655500 12000000.0 .000700000 12100000.0 .0007320004850 3107 66 12200000.0 .000768000 12300000.0 .000808000 12400000.0 .0008520004850 3107 67 12500000.0 .000900000 12600000.0 .000952000 12700000.0 .0010080004850 3107 68 12800000.0 .001068000 12900000.0 .001132000 13000000.0 .0012000004850 3107 69 13200000.0 .001364000 13400000.0 .001536000 13600000.0 .0017160004850 3107 70 13800000.0 .001904000 14100000.0 .002201000 14400000.0 .0025160004850 3107 71 14700000.0 .002849000 15000000.0 .003200000 15500000.0 .0038620004850 3107 72 16300000.0 .004881000 16700000.0 .005361000 17100000.0 .0058090004850 3107 73 17600000.0 .006324000 18100000.0 .006789000 18600000.0 .0072040004850 3107 74 19100000.0 .007567000 19700000.0 .007936000 20000000.0 .0081000004850 3107 75 4850 3 0 76 4850 0 0 77 0 0 0 78 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0