IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 5.01000E+3 9.92692E+0 0 0 1 1 530 1451 1 0.0 0.0 0 0 0 0 530 1451 2 0.0 0.0 0 0 48 2 530 1451 3 5-B - 10 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL. 530 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 530 1451 5 IDENTIFIER=INDL 0530 REV1 530 1451 6 FORMAT= ENDF/B-5 530 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 530 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 530 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 530 1451 10 TEXT= 530 1451 11 5-B-10(N,T)4-BE-8 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 530 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 530 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 530 1451 14 OBNINSK,USSR). 530 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 530 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 530 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 530 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 530 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 530 1451 20 KONSTANTY,32(1),PAGE 105,1979 530 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 530 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 530 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 530 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 530 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 530 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 530 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP. 530 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 530 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 530 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 530 1451 31 -------------|-------------|---------------|------------------ 530 1451 32 5-B-10(N,T) | 23.8 | 23.4 | 22.6 530 1451 33 ***************** Program LINEAR (VERSION 2002-1) *************** 530 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 530 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 530 1451 36 ***************** Program FIXUP (Version 2002-1) **************** 530 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 530 1451 38 Corrected Thresholds-----------------------------------------Yes 530 1451 39 Extended Cross Sections to 20 MeV----------------------------No 530 1451 40 Allow Cross Section Deletion---------------------------------No 530 1451 41 Allow Cross Section Reconstruction---------------------------No 530 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 530 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 530 1451 44 Deleted Duplicate Points-------------------------------------Yes 530 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 530 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 530 1451 47 Allow Creation of Missing Sections---------------------------No 530 1451 48 Allow Insertion of Energy Points-----------------------------No 530 1451 49 Create Uniform Energy Grid-----------------------------------No 530 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 530 1451 51 1 451 53 1 530 1451 52 3 105 24 1 530 1451 53 530 1 0 54 530 0 0 55 5.01000E+3 9.92692E+0 0 0 0 0 530 3105 56 2.93000E+2 2.10000E+5 0 0 1 62 530 3105 57 62 2 530 3105 58 1200000.00 0.0 1300000.00 .001000000 1500000.00 .009000000 530 3105 59 1700000.00 .016000000 1800000.00 .017500000 1900000.00 .020000000 530 3105 60 2000000.00 .020000000 2100000.00 .019610000 2200000.00 .019480000 530 3105 61 2300000.00 .019620000 2400000.00 .020020000 2500000.00 .020690000 530 3105 62 2600000.00 .021620000 2700000.00 .022820000 2800000.00 .024280000 530 3105 63 2900000.00 .026010000 3000000.00 .028000000 3100000.00 .029740000 530 3105 64 3200000.00 .031860000 3300000.00 .034360000 3400000.00 .037240000 530 3105 65 3500000.00 .040500000 3600000.00 .044140000 3700000.00 .048160000 530 3105 66 3800000.00 .052560000 3900000.00 .057340000 4000000.00 .062500000 530 3105 67 4100000.00 .072340000 4200000.00 .081600000 4300000.00 .090290000 530 3105 68 4400000.00 .098400000 4500000.00 .105900000 4600000.00 .112900000 530 3105 69 4700000.00 .119300000 4800000.00 .125100000 4900000.00 .130300000 530 3105 70 5000000.00 .135000000 5200000.00 .139400000 5400000.00 .143200000 530 3105 71 5600000.00 .146200000 5800000.00 .148400000 6000000.00 .150000000 530 3105 72 6100000.00 .150000000 6500000.00 .149200000 6900000.00 .147600000 530 3105 73 7000000.00 .147000000 7600000.00 .141400000 8000000.00 .138000000 530 3105 74 9000000.00 .131000000 9700000.00 .127000000 10200000.0 .123500000 530 3105 75 12400000.0 .107000000 13000000.0 .103000000 13600000.0 .099820000 530 3105 76 14100000.0 .096830000 15500000.0 .087870000 16100000.0 .084500000 530 3105 77 18200000.0 .074080000 18900000.0 .070540000 19000000.0 .070000000 530 3105 78 19500000.0 .066750000 20000000.0 .064000000 530 3105 79 530 3 0 80 530 0 0 81 0 0 0 82 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0