IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 6.01200E+3 1.18969E+1 0 0 1 1 630 1451 1 0.0 0.0 0 0 0 0 630 1451 2 0.0 0.0 0 0 48 2 630 1451 3 6-C - 12 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL. 630 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 630 1451 5 IDENTIFIER=INDL 0630 REV1 630 1451 6 FORMAT= ENDF/B-5 630 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 630 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 630 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 630 1451 10 TEXT= 630 1451 11 6-C-12(N,P)5-B-12 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 630 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 630 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 630 1451 14 OBNINSK,USSR). 630 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 630 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 630 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 630 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 630 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 630 1451 20 KONSTANTY,32(1),PAGE 105,1979 630 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 630 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 630 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 630 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 630 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 630 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 630 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP. 630 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 630 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 630 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 630 1451 31 -------------|-------------|---------------|------------------ 630 1451 32 6-C-12(N,P) | 0.26E-03 | 0.20E-03 | 0.47E-03 630 1451 33 ***************** Program LINEAR (VERSION 2002-1) *************** 630 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 630 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 630 1451 36 ***************** Program FIXUP (Version 2002-1) **************** 630 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 630 1451 38 Corrected Thresholds-----------------------------------------Yes 630 1451 39 Extended Cross Sections to 20 MeV----------------------------No 630 1451 40 Allow Cross Section Deletion---------------------------------No 630 1451 41 Allow Cross Section Reconstruction---------------------------No 630 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 630 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 630 1451 44 Deleted Duplicate Points-------------------------------------Yes 630 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 630 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 630 1451 47 Allow Creation of Missing Sections---------------------------No 630 1451 48 Allow Insertion of Energy Points-----------------------------No 630 1451 49 Create Uniform Energy Grid-----------------------------------No 630 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 630 1451 51 1 451 53 1 630 1451 52 3 103 17 1 630 1451 53 630 1 0 54 630 0 0 55 6.01200E+3 1.18969E+1 0 0 0 0 630 3103 56 2.93000E+2-1.25800E+7 0 0 1 42 630 3103 57 42 2 630 3103 58 13637418.3 0.0 14300000.0 0.0 14400000.0 6.00000E-5 630 3103 59 14500000.0 .000187500 14600000.0 .000360000 14700000.0 .000577500 630 3103 60 14800000.0 .000840000 14900000.0 .001147000 15000000.0 .001500000 630 3103 61 15100000.0 .000907500 15200000.0 .000580000 15300000.0 .000517500 630 3103 62 15400000.0 .000720000 15500000.0 .001188000 15600000.0 .001920000 630 3103 63 15700000.0 .002917000 15800000.0 .004180000 15900000.0 .005707000 630 3103 64 16000000.0 .007500000 16100000.0 .008100000 16200000.0 .010250000 630 3103 65 16300000.0 .013500000 16400000.0 .018000000 16500000.0 .023000000 630 3103 66 16600000.0 .027500000 16700000.0 .030250000 16800000.0 .030100000 630 3103 67 16900000.0 .029200000 17000000.0 .028450000 17100000.0 .029300000 630 3103 68 17200000.0 .033300000 17300000.0 .036300000 17400000.0 .038400000 630 3103 69 17500000.0 .039500000 17600000.0 .039750000 17700000.0 .039500000 630 3103 70 17800000.0 .039000000 18000000.0 .037500000 19000000.0 .032500000 630 3103 71 19400000.0 .030380000 19800000.0 .028420000 20000000.0 .027500000 630 3103 72 630 3 0 73 630 0 0 74 0 0 0 75 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0