IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 3.70870E+4 8.61626E+1 0 0 1 13740 1451 1 0.0 0.0 0 0 0 03740 1451 2 0.0 0.0 0 0 48 23740 1451 3 37-Rb- 87 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.3740 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 3740 1451 5 IDENTIFIER=INDL 3740 REV1 3740 1451 6 FORMAT= ENDF/B-5 3740 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 3740 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 3740 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 3740 1451 10 TEXT= 3740 1451 11 37-RB-87(N,2N)37-RB-86 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 3740 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 3740 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 3740 1451 14 OBNINSK,USSR). 3740 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 3740 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 3740 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 3740 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 3740 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 3740 1451 20 KONSTANTY,32(1),PAGE 105,1979 3740 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 3740 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 3740 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 3740 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 3740 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 3740 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 3740 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.3740 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 3740 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 3740 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 3740 1451 31 -------------|-------------|---------------|------------------ 3740 1451 32 37-RB-87(N,2N) | 0.372 | 0.313 | 0.476 3740 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************3740 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 3740 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 3740 1451 36 ***************** Program FIXUP (Version 2002-1) ****************3740 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 3740 1451 38 Corrected Thresholds-----------------------------------------Yes 3740 1451 39 Extended Cross Sections to 20 MeV----------------------------No 3740 1451 40 Allow Cross Section Deletion---------------------------------No 3740 1451 41 Allow Cross Section Reconstruction---------------------------No 3740 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 3740 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 3740 1451 44 Deleted Duplicate Points-------------------------------------Yes 3740 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 3740 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 3740 1451 47 Allow Creation of Missing Sections---------------------------No 3740 1451 48 Allow Insertion of Energy Points-----------------------------No 3740 1451 49 Create Uniform Energy Grid-----------------------------------No 3740 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 3740 1451 51 1 451 53 13740 1451 52 3 16 14 13740 1451 53 3740 1 0 54 3740 0 0 55 3.70870E+4 8.61626E+1 0 1 0 03740 3 16 56 2.93000E+2-9.92000E+6 0 0 1 323740 3 16 57 32 2 3740 3 16 58 10035131.2 0.0 10400000.0 0.0 10500000.0 .0150000003740 3 16 59 10600000.0 .060000000 10700000.0 .095000000 10800000.0 .1400000003740 3 16 60 11000000.0 .220000000 11100000.0 .260700000 11300000.0 .3403000003740 3 16 61 11500000.0 .417500000 11700000.0 .492300000 11900000.0 .5647000003740 3 16 62 12000000.0 .600000000 12200000.0 .673600000 12400000.0 .7424000003740 3 16 63 12600000.0 .806400000 12800000.0 .865600000 13000000.0 .9200000003740 3 16 64 13300000.0 .987300000 13500000.0 1.02900000 13800000.0 1.086000003740 3 16 65 14100000.0 1.13700000 14400000.0 1.18200000 14600000.0 1.208000003740 3 16 66 14900000.0 1.24100000 15200000.0 1.27000000 15500000.0 1.285000003740 3 16 67 17000000.0 1.33000000 18100000.0 1.34200000 18900000.0 1.350000003740 3 16 68 19000000.0 1.35000000 20000000.0 1.34000000 3740 3 16 69 3740 3 0 70 3740 0 0 71 0 0 0 72 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0