IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 4.81110E+4 1.09951E+2 0 0 1 14840 1451 1 0.0 0.0 0 0 0 04840 1451 2 0.0 0.0 0 0 48 24840 1451 3 48-Cd-111 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.4840 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 4840 1451 5 IDENTIFIER=INDL 4840 REV1 4840 1451 6 FORMAT= ENDF/B-5 4840 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 4840 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 4840 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 4840 1451 10 TEXT= 4840 1451 11 48-CD-111(N,P)47-AG-111 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 4840 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 4840 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 4840 1451 14 OBNINSK,USSR). 4840 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 4840 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 4840 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 4840 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 4840 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 4840 1451 20 KONSTANTY,32(1),PAGE 105,1979 4840 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 4840 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 4840 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 4840 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 4840 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 4840 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 4840 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.4840 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 4840 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 4840 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 4840 1451 31 -------------|-------------|---------------|------------------ 4840 1451 32 48-CD-111(N,P) | 0.020 | 0.018 | 0.023 4840 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************4840 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 4840 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 4840 1451 36 ***************** Program FIXUP (Version 2002-1) ****************4840 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 4840 1451 38 Corrected Thresholds-----------------------------------------Yes 4840 1451 39 Extended Cross Sections to 20 MeV----------------------------No 4840 1451 40 Allow Cross Section Deletion---------------------------------No 4840 1451 41 Allow Cross Section Reconstruction---------------------------No 4840 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 4840 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 4840 1451 44 Deleted Duplicate Points-------------------------------------Yes 4840 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 4840 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 4840 1451 47 Allow Creation of Missing Sections---------------------------No 4840 1451 48 Allow Insertion of Energy Points-----------------------------No 4840 1451 49 Create Uniform Energy Grid-----------------------------------No 4840 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 4840 1451 51 1 451 53 14840 1451 52 3 103 18 14840 1451 53 4840 1 0 54 4840 0 0 55 4.81110E+4 1.09951E+2 0 1 0 04840 3103 56 2.93000E+2-2.48000E+5 0 0 1 434840 3103 57 43 2 4840 3103 58 250255.550 0.0 7300000.00 0.0 7400000.00 2.00000E-54840 3103 59 7500000.00 6.25000E-5 7600000.00 .000120000 7700000.00 .0001925004840 3103 60 7800000.00 .000280000 7900000.00 .000382500 8000000.00 .0005000004840 3103 61 9000000.00 .002500000 9100000.00 .002655000 9200000.00 .0028200004840 3103 62 9300000.00 .002995000 9400000.00 .003180000 9500000.00 .0033750004840 3103 63 9600000.00 .003580000 9700000.00 .003795000 9800000.00 .0040200004840 3103 64 9900000.00 .004255000 10000000.0 .004500000 11000000.0 .0075000004840 3103 65 11100000.0 .007732000 11300000.0 .008242000 11500000.0 .0088120004840 3103 66 11700000.0 .009442000 11900000.0 .010130000 12000000.0 .0105000004840 3103 67 13000000.0 .015000000 13400000.0 .016740000 13900000.0 .0190300004840 3103 68 14000000.0 .019500000 14400000.0 .021620000 14800000.0 .0235800004840 3103 69 15200000.0 .025380000 15600000.0 .027020000 16200000.0 .0292200004840 3103 70 16500000.0 .030190000 16900000.0 .031270000 17100000.0 .0316700004840 3103 71 17800000.0 .032740000 18500000.0 .033560000 19000000.0 .0340000004840 3103 72 20000000.0 .034500000 4840 3103 73 4840 3 0 74 4840 0 0 75 0 0 0 76 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0