IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 3.00600E+3 5.96345E+0 0 0 1 1 330 1451 1 0.0 0.0 0 0 0 0 330 1451 2 0.0 0.0 0 0 50 3 330 1451 3 3-Li- 6 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL. 330 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 330 1451 5 IDENTIFIER=INDL 0330 REV1 330 1451 6 FORMAT= ENDF/B-5 330 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 330 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 330 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 330 1451 10 TEXT= 330 1451 11 3-LI-6(N,P)2-HE-6 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 330 1451 12 3-LI-6(N,2N)3-LI-5 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 330 1451 13 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 330 1451 14 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 330 1451 15 OBNINSK,USSR). 330 1451 16 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 330 1451 17 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 330 1451 18 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 330 1451 19 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 330 1451 20 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 330 1451 21 KONSTANTY,32(1),PAGE 105,1979 330 1451 22 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 330 1451 23 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 330 1451 24 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 330 1451 25 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 330 1451 26 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 330 1451 27 YAD. KOSTANTY 3,(42),P.60,(1981) 330 1451 28 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP. 330 1451 29 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 330 1451 30 REACTION | V.2,P.271,IAEA,VIENNA) 330 1451 31 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 330 1451 32 -------------|-------------|---------------|------------------ 330 1451 33 3-LI-6(N,P) | 4.18 | 4.09 | 3.91 330 1451 34 3-LI-6(N,2N) | 0.158 | 0.142 | 0.173 330 1451 35 ***************** Program LINEAR (VERSION 2002-1) *************** 330 1451 36 For All Data Greater than 1.0000E-10 barns in Absolute Value 330 1451 37 Data Linearized to Within an Accuracy of .100000000 per-cent 330 1451 38 ***************** Program FIXUP (Version 2002-1) **************** 330 1451 39 Corrected ZA/AWR in All Sections-----------------------------Yes 330 1451 40 Corrected Thresholds-----------------------------------------Yes 330 1451 41 Extended Cross Sections to 20 MeV----------------------------No 330 1451 42 Allow Cross Section Deletion---------------------------------No 330 1451 43 Allow Cross Section Reconstruction---------------------------No 330 1451 44 Make All Cross Sections Non-Negative-------------------------Yes 330 1451 45 Delete Energies Not in Ascending Order-----------------------Yes 330 1451 46 Deleted Duplicate Points-------------------------------------Yes 330 1451 47 Check for Ascending MAT/MF/MT Order--------------------------Yes 330 1451 48 Check for Legal MF/MT Numbers--------------------------------Yes 330 1451 49 Allow Creation of Missing Sections---------------------------No 330 1451 50 Allow Insertion of Energy Points-----------------------------No 330 1451 51 Create Uniform Energy Grid-----------------------------------No 330 1451 52 Delete Section if Cross Section =0 at All Energies-----------Yes 330 1451 53 1 451 56 1 330 1451 54 3 16 13 1 330 1451 55 3 103 21 1 330 1451 56 330 1 0 57 330 0 0 58 3.00600E+3 5.96345E+0 0 0 0 0 330 3 16 59 2.93000E+2-5.66000E+6 0 0 1 28 330 3 16 60 28 2 330 3 16 61 6609115.03 0.0 7200000.00 0.0 7500000.00 .003000000 330 3 16 62 7600000.00 .004500000 7700000.00 .005500000 7800000.00 .007000000 330 3 16 63 8000000.00 .009000000 9000000.00 .021000000 9400000.00 .025920000 330 3 16 64 9800000.00 .030680000 10000000.0 .033000000 11000000.0 .044000000 330 3 16 65 11400000.0 .048640000 11800000.0 .052960000 12300000.0 .058010000 330 3 16 66 12600000.0 .060760000 13000000.0 .064000000 13500000.0 .067250000 330 3 16 67 14000000.0 .070000000 14700000.0 .072690000 15000000.0 .074000000 330 3 16 68 15700000.0 .077600000 16400000.0 .080720000 17000000.0 .083000000 330 3 16 69 18400000.0 .087080000 19000000.0 .089000000 19800000.0 .092280000 330 3 16 70 20000000.0 .093000000 330 3 16 71 330 3 0 72 3.00600E+3 5.96345E+0 0 0 0 0 330 3103 73 2.93000E+2-2.72000E+6 0 0 1 53 330 3103 74 53 2 330 3103 75 3176111.81 0.0 3200000.00 0.0 3300000.00 .002000000 330 3103 76 3400000.00 .005000000 3500000.00 .013000000 3600000.00 .018500000 330 3103 77 3700000.00 .023500000 3800000.00 .028000000 4000000.00 .035000000 330 3103 78 4100000.00 .036700000 4200000.00 .036700000 4300000.00 .035500000 330 3103 79 4400000.00 .033700000 4500000.00 .031300000 4600000.00 .027800000 330 3103 80 4700000.00 .027000000 4800000.00 .028700000 4900000.00 .030300000 330 3103 81 5000000.00 .030500000 5100000.00 .029310000 5300000.00 .027090000 330 3103 82 5400000.00 .026060000 5600000.00 .024160000 5700000.00 .023290000 330 3103 83 5900000.00 .021710000 6000000.00 .021000000 6200000.00 .019990000 330 3103 84 6400000.00 .019070000 6600000.00 .018230000 6800000.00 .017470000 330 3103 85 7000000.00 .016800000 7400000.00 .015850000 7700000.00 .015240000 330 3103 86 8000000.00 .014700000 9000000.00 .013500000 9500000.00 .012850000 330 3103 87 10000000.0 .012300000 10500000.0 .011920000 10900000.0 .011590000 330 3103 88 11100000.0 .011390000 11500000.0 .010970000 12000000.0 .010500000 330 3103 89 12900000.0 .009775000 14800000.0 .008432000 15100000.0 .008222000 330 3103 90 15500000.0 .007950000 15800000.0 .007788000 16000000.0 .007700000 330 3103 91 17200000.0 .007468000 17900000.0 .007324000 18800000.0 .007052000 330 3103 92 19500000.0 .006887000 20000000.0 .006800000 330 3103 93 330 3 0 94 330 0 0 95 0 0 0 96 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0