IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 3.10690E+4 6.83335E+1 0 0 1 13130 1451 1 0.0 0.0 0 0 0 03130 1451 2 0.0 0.0 0 0 48 33130 1451 3 31-Ga- 69 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.3130 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 3130 1451 5 IDENTIFIER=INDL 3130 REV1 3130 1451 6 FORMAT= ENDF/B-5 3130 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 3130 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 3130 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 3130 1451 10 TEXT= 3130 1451 11 31-GA-69(N,2N)31-GA-68 EN.REG. UP TO 20.MEV IN STEPS OF 100.KEV 3130 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 3130 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 3130 1451 14 OBNINSK,USSR). 3130 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 3130 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 3130 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 3130 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 3130 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 3130 1451 20 KONSTANTY,32(1),PAGE 105,1979 3130 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 3130 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 3130 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 3130 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 3130 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 3130 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 3130 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.3130 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 3130 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 3130 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 3130 1451 31 -------------|-------------|---------------|------------------ 3130 1451 32 31-GA-69(N,2N) | 0.227 | 0.189 | 0.299 3130 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************3130 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 3130 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 3130 1451 36 ***************** Program FIXUP (Version 2002-1) ****************3130 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 3130 1451 38 Corrected Thresholds-----------------------------------------Yes 3130 1451 39 Extended Cross Sections to 20 MeV----------------------------No 3130 1451 40 Allow Cross Section Deletion---------------------------------No 3130 1451 41 Allow Cross Section Reconstruction---------------------------No 3130 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 3130 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 3130 1451 44 Deleted Duplicate Points-------------------------------------Yes 3130 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 3130 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 3130 1451 47 Allow Creation of Missing Sections---------------------------No 3130 1451 48 Allow Insertion of Energy Points-----------------------------No 3130 1451 49 Create Uniform Energy Grid-----------------------------------No 3130 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 3130 1451 51 1 451 54 13130 1451 52 3 16 12 13130 1451 53 3 103 8 13130 1451 54 3130 1 0 55 3130 0 0 56 3.10690E+4 6.83335E+1 0 0 0 03130 3 16 57 2.93000E+2-1.03100E+7 0 0 1 273130 3 16 58 27 2 3130 3 16 59 10460000.0 0.0 10600000.0 .010000000 10800000.0 .0300000003130 3 16 60 11000000.0 .070000000 11400000.0 .181400000 12000000.0 .3500000003130 3 16 61 12200000.0 .411400000 12400000.0 .470600000 12600000.0 .5276000003130 3 16 62 12800000.0 .582400000 13200000.0 .687400000 13400000.0 .7366000003130 3 16 63 13600000.0 .782600000 13900000.0 .845600000 14000000.0 .8650000003130 3 16 64 14300000.0 .915200000 14600000.0 .961000000 14900000.0 1.002000003130 3 16 65 15200000.0 1.03800000 15600000.0 1.08000000 16000000.0 1.115000003130 3 16 66 16600000.0 1.15300000 17300000.0 1.19100000 17800000.0 1.213000003130 3 16 67 18600000.0 1.23700000 19100000.0 1.24600000 20000000.0 1.255000003130 3 16 68 3130 3 0 69 3.10690E+4 6.83335E+1 0 0 0 03130 3103 70 2.93000E+2-1.02400E+5 0 0 1 133130 3103 71 13 2 3130 3103 72 103898.533 0.0 4700000.00 0.0 5500000.00 .0016000003130 3103 73 6000000.00 .003000000 8000000.00 .009000000 10000000.0 .0170000003130 3103 74 11000000.0 .022000000 12000000.0 .026000000 13000000.0 .0270000003130 3103 75 14000000.0 .026000000 17000000.0 .020000000 18000000.0 .0170000003130 3103 76 20000000.0 .013000000 3130 3103 77 3130 3 0 78 3130 0 0 79 0 0 0 80 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0