IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 8.01600E+3 1.58575E+1 0 0 1 1 830 1451 1 0.0 0.0 0 0 0 0 830 1451 2 0.0 0.0 0 0 50 2 830 1451 3 8-O - 16 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL. 830 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 830 1451 5 IDENTIFIER=INDL 0830 REV1 830 1451 6 FORMAT= ENDF/B-5 830 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 830 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 830 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 830 1451 10 TEXT= 830 1451 11 8-O-16(N,P)7-N-16 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 830 1451 12 8-O-16(N,A)6-C-13 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 830 1451 13 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 830 1451 14 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 830 1451 15 OBNINSK,USSR). 830 1451 16 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 830 1451 17 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 830 1451 18 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 830 1451 19 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 830 1451 20 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 830 1451 21 KONSTANTY,32(1),PAGE 105,1979 830 1451 22 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 830 1451 23 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 830 1451 24 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 830 1451 25 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 830 1451 26 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 830 1451 27 YAD. KOSTANTY 3,(42),P.60,(1981) 830 1451 28 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP. 830 1451 29 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 830 1451 30 REACTION | V.2,P.271,IAEA,VIENNA) 830 1451 31 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 830 1451 32 -------------|-------------|---------------|------------------ 830 1451 33 8-O-16(N,P) | 0.019 | 0.016 | 0.024 830 1451 34 8-O-16(N,A) | 11.3 | 11.0 | 10.7 830 1451 35 ***************** Program LINEAR (VERSION 2002-1) *************** 830 1451 36 For All Data Greater than 1.0000E-10 barns in Absolute Value 830 1451 37 Data Linearized to Within an Accuracy of .100000000 per-cent 830 1451 38 ***************** Program FIXUP (Version 2002-1) **************** 830 1451 39 Corrected ZA/AWR in All Sections-----------------------------Yes 830 1451 40 Corrected Thresholds-----------------------------------------Yes 830 1451 41 Extended Cross Sections to 20 MeV----------------------------No 830 1451 42 Allow Cross Section Deletion---------------------------------No 830 1451 43 Allow Cross Section Reconstruction---------------------------No 830 1451 44 Make All Cross Sections Non-Negative-------------------------Yes 830 1451 45 Delete Energies Not in Ascending Order-----------------------Yes 830 1451 46 Deleted Duplicate Points-------------------------------------Yes 830 1451 47 Check for Ascending MAT/MF/MT Order--------------------------Yes 830 1451 48 Check for Legal MF/MT Numbers--------------------------------Yes 830 1451 49 Allow Creation of Missing Sections---------------------------No 830 1451 50 Allow Insertion of Energy Points-----------------------------No 830 1451 51 Create Uniform Energy Grid-----------------------------------No 830 1451 52 Delete Section if Cross Section =0 at All Energies-----------Yes 830 1451 53 1 451 55 1 830 1451 54 3 103 19 1 830 1451 55 830 1 0 56 830 0 0 57 8.01600E+3 1.58575E+1 0 0 0 0 830 3103 58 2.93000E+2-9.63300E+6 0 0 1 48 830 3103 59 48 2 830 3103 60 10240000.0 0.0 10700000.0 0.0 10800000.0 .001000000 830 3103 61 11000000.0 .007000000 11200000.0 .014000000 11300000.0 .019000000 830 3103 62 11400000.0 .026000000 11500000.0 .034500000 11600000.0 .047500000 830 3103 63 11700000.0 .063500000 11800000.0 .078500000 11900000.0 .072500000 830 3103 64 12000000.0 .050000000 12100000.0 .031500000 12200000.0 .025000000 830 3103 65 12300000.0 .023300000 12400000.0 .023000000 12500000.0 .023300000 830 3103 66 12600000.0 .024000000 12700000.0 .025000000 12800000.0 .026700000 830 3103 67 12900000.0 .029000000 13000000.0 .032000000 13100000.0 .034140000 830 3103 68 13200000.0 .036080000 13300000.0 .037820000 13400000.0 .039370000 830 3103 69 13500000.0 .040720000 13600000.0 .041870000 13700000.0 .042820000 830 3103 70 13800000.0 .043580000 13900000.0 .044140000 14000000.0 .044500000 830 3103 71 14400000.0 .041360000 14700000.0 .039210000 15000000.0 .037250000 830 3103 72 15600000.0 .034010000 16300000.0 .030490000 16600000.0 .029120000 830 3103 73 16900000.0 .027880000 17200000.0 .026780000 17500000.0 .025810000 830 3103 74 17800000.0 .024980000 18000000.0 .024500000 18600000.0 .023540000 830 3103 75 19200000.0 .022760000 19800000.0 .022160000 20000000.0 .022000000 830 3103 76 830 3 0 77 830 0 0 78 0 0 0 79 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0