IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 3.10710E+4 7.03154E+1 0 0 1 13140 1451 1 0.0 0.0 0 0 0 03140 1451 2 0.0 0.0 0 0 48 23140 1451 3 31-Ga- 71 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.3140 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 3140 1451 5 IDENTIFIER=INDL 3140 REV1 3140 1451 6 FORMAT= ENDF/B-5 3140 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 3140 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 3140 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 3140 1451 10 TEXT= 3140 1451 11 31-GA-71(N,2N)31-GA-70 EN.REG. UP TO 20.MEV IN STEPS OF 100.KEV 3140 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 3140 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 3140 1451 14 OBNINSK,USSR). 3140 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 3140 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 3140 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 3140 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 3140 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 3140 1451 20 KONSTANTY,32(1),PAGE 105,1979 3140 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 3140 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 3140 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 3140 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 3140 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 3140 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 3140 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.3140 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 3140 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 3140 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 3140 1451 31 -------------|-------------|---------------|------------------ 3140 1451 32 31-GA-71(N,2N) | 0.617 | 0.527 | 0.758 3140 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************3140 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 3140 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 3140 1451 36 ***************** Program FIXUP (Version 2002-1) ****************3140 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 3140 1451 38 Corrected Thresholds-----------------------------------------Yes 3140 1451 39 Extended Cross Sections to 20 MeV----------------------------No 3140 1451 40 Allow Cross Section Deletion---------------------------------No 3140 1451 41 Allow Cross Section Reconstruction---------------------------No 3140 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 3140 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 3140 1451 44 Deleted Duplicate Points-------------------------------------Yes 3140 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 3140 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 3140 1451 47 Allow Creation of Missing Sections---------------------------No 3140 1451 48 Allow Insertion of Energy Points-----------------------------No 3140 1451 49 Create Uniform Energy Grid-----------------------------------No 3140 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 3140 1451 51 1 451 53 13140 1451 52 3 16 16 13140 1451 53 3140 1 0 54 3140 0 0 55 3.10710E+4 7.03154E+1 0 0 0 03140 3 16 56 2.93000E+2-9.31000E+6 0 0 1 393140 3 16 57 39 2 3140 3 16 58 9442403.43 0.0 9700000.00 0.0 9800000.00 .0270000003140 3 16 59 9900000.00 .066000000 10000000.0 .099000000 10100000.0 .1407000003140 3 16 60 10200000.0 .181400000 10300000.0 .221200000 10400000.0 .2600000003140 3 16 61 10500000.0 .297900000 10600000.0 .334800000 10700000.0 .3708000003140 3 16 62 10800000.0 .405800000 10900000.0 .439900000 11000000.0 .4730000003140 3 16 63 11200000.0 .534100000 11400000.0 .592500000 11600000.0 .6483000003140 3 16 64 11900000.0 .727100000 12200000.0 .800900000 12500000.0 .8684000003140 3 16 65 12800000.0 .928700000 13000000.0 .965000000 13300000.0 1.010000003140 3 16 66 13700000.0 1.06400000 14000000.0 1.09900000 14400000.0 1.137000003140 3 16 67 14900000.0 1.17700000 15400000.0 1.20700000 15800000.0 1.226000003140 3 16 68 16300000.0 1.24400000 16700000.0 1.25100000 16900000.0 1.251000003140 3 16 69 17100000.0 1.24700000 17800000.0 1.22200000 18400000.0 1.195000003140 3 16 70 18800000.0 1.17300000 19100000.0 1.15200000 20000000.0 1.080000003140 3 16 71 3140 3 0 72 3140 0 0 73 0 0 0 74 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0