IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 3.90890E+4 8.81421E+1 0 0 1 13930 1451 1 0.0 0.0 0 0 0 03930 1451 2 0.0 0.0 0 0 48 33930 1451 3 39-Y - 89 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.3930 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 3930 1451 5 IDENTIFIER=INDL 3930 REV1 3930 1451 6 FORMAT= ENDF/B-5 3930 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 3930 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 3930 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 3930 1451 10 TEXT= 3930 1451 11 39-Y-89(N,2N)39-Y-88 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 3930 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 3930 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 3930 1451 14 OBNINSK,USSR). 3930 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 3930 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 3930 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 3930 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 3930 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 3930 1451 20 KONSTANTY,32(1),PAGE 105,1979 3930 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 3930 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 3930 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 3930 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 3930 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 3930 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 3930 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.3930 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 3930 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 3930 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 3930 1451 31 -------------|-------------|---------------|------------------ 3930 1451 32 39-Y-89(N,2N) | 0.126 | 0.103 | 0.177 3930 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************3930 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 3930 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 3930 1451 36 ***************** Program FIXUP (Version 2002-1) ****************3930 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 3930 1451 38 Corrected Thresholds-----------------------------------------Yes 3930 1451 39 Extended Cross Sections to 20 MeV----------------------------No 3930 1451 40 Allow Cross Section Deletion---------------------------------No 3930 1451 41 Allow Cross Section Reconstruction---------------------------No 3930 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 3930 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 3930 1451 44 Deleted Duplicate Points-------------------------------------Yes 3930 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 3930 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 3930 1451 47 Allow Creation of Missing Sections---------------------------No 3930 1451 48 Allow Insertion of Energy Points-----------------------------No 3930 1451 49 Create Uniform Energy Grid-----------------------------------No 3930 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 3930 1451 51 1 451 54 13930 1451 52 3 16 16 13930 1451 53 3 103 8 13930 1451 54 3930 1 0 55 3930 0 0 56 3.90890E+4 8.81421E+1 0 1 0 03930 3 16 57 2.93000E+2-1.14700E+7 0 0 1 373930 3 16 58 37 2 3930 3 16 59 11600000.0 0.0 11800000.0 0.0 11900000.0 .0050000003930 3 16 60 12000000.0 .025000000 12100000.0 .079570000 12200000.0 .1328000003930 3 16 61 12300000.0 .184700000 12400000.0 .235200000 12500000.0 .2844000003930 3 16 62 12600000.0 .332200000 12700000.0 .378700000 12800000.0 .4238000003930 3 16 63 12900000.0 .467600000 13100000.0 .552200000 13200000.0 .5928000003930 3 16 64 13300000.0 .631800000 13400000.0 .669200000 13500000.0 .7050000003930 3 16 65 13600000.0 .739200000 13700000.0 .771800000 13900000.0 .8322000003930 3 16 66 14000000.0 .860000000 14300000.0 .925900000 14600000.0 .9842000003930 3 16 67 14900000.0 1.03500000 15200000.0 1.07800000 15500000.0 1.113000003930 3 16 68 15800000.0 1.14100000 16000000.0 1.15500000 16500000.0 1.170000003930 3 16 69 17000000.0 1.17500000 17400000.0 1.16900000 17900000.0 1.158000003930 3 16 70 18500000.0 1.13700000 19300000.0 1.10100000 19800000.0 1.073000003930 3 16 71 20000000.0 1.06000000 3930 3 16 72 3930 3 0 73 3.90890E+4 8.81421E+1 0 1 0 03930 3103 74 2.93000E+2-7.07000E+5 0 0 1 153930 3103 75 15 2 3930 3103 76 715000.000 0.0 5000000.00 0.0 6000000.00 .0008000003930 3103 77 7000000.00 .002000000 8000000.00 .004000000 9000000.00 .0070000003930 3103 78 11000000.0 .015000000 12000000.0 .020000000 14000000.0 .0240000003930 3103 79 15000000.0 .025000000 16000000.0 .025000000 17000000.0 .0240000003930 3103 80 18000000.0 .024000000 19000000.0 .022000000 20000000.0 .0210000003930 3103 81 3930 3 0 82 3930 0 0 83 0 0 0 84 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0