IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 3.70850E+4 8.41824E+1 0 0 1 13730 1451 1 0.0 0.0 0 0 0 03730 1451 2 0.0 0.0 0 0 48 33730 1451 3 37-Rb- 85 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.3730 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 3730 1451 5 IDENTIFIER=INDL 3730 REV1 3730 1451 6 FORMAT= ENDF/B-5 3730 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 3730 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 3730 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 3730 1451 10 TEXT= 3730 1451 11 37-RB-85(N,2N)37-RB-84 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 3730 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 3730 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 3730 1451 14 OBNINSK,USSR). 3730 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 3730 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 3730 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 3730 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 3730 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 3730 1451 20 KONSTANTY,32(1),PAGE 105,1979 3730 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 3730 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 3730 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 3730 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 3730 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 3730 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 3730 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.3730 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 3730 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 3730 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 3730 1451 31 -------------|-------------|---------------|------------------ 3730 1451 32 37-RB-85(N,2N) | 0.27 | 0.22 | 0.35 3730 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************3730 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 3730 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 3730 1451 36 ***************** Program FIXUP (Version 2002-1) ****************3730 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 3730 1451 38 Corrected Thresholds-----------------------------------------Yes 3730 1451 39 Extended Cross Sections to 20 MeV----------------------------No 3730 1451 40 Allow Cross Section Deletion---------------------------------No 3730 1451 41 Allow Cross Section Reconstruction---------------------------No 3730 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 3730 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 3730 1451 44 Deleted Duplicate Points-------------------------------------Yes 3730 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 3730 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 3730 1451 47 Allow Creation of Missing Sections---------------------------No 3730 1451 48 Allow Insertion of Energy Points-----------------------------No 3730 1451 49 Create Uniform Energy Grid-----------------------------------No 3730 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 3730 1451 51 1 451 54 13730 1451 52 3 16 15 13730 1451 53 3 107 7 13730 1451 54 3730 1 0 55 3730 0 0 56 3.70850E+4 8.41824E+1 0 1 0 03730 3 16 57 2.93000E+2-1.04800E+7 0 0 1 363730 3 16 58 36 2 3730 3 16 59 10604491.6 0.0 10700000.0 0.0 10800000.0 .0120000003730 3 16 60 10900000.0 .036000000 11000000.0 .064000000 11100000.0 .0989200003730 3 16 61 11300000.0 .169500000 11500000.0 .241000000 11800000.0 .3501000003730 3 16 62 12000000.0 .424000000 12100000.0 .468900000 12200000.0 .5123000003730 3 16 63 12300000.0 .554300000 12400000.0 .594900000 12500000.0 .6340000003730 3 16 64 12600000.0 .671700000 12800000.0 .742700000 13000000.0 .8080000003730 3 16 65 13200000.0 .865000000 13400000.0 .917400000 13600000.0 .9654000003730 3 16 66 13800000.0 1.00900000 14000000.0 1.04800000 14200000.0 1.080000003730 3 16 67 14400000.0 1.11000000 14700000.0 1.14700000 15000000.0 1.176000003730 3 16 68 15400000.0 1.19600000 15800000.0 1.21100000 16200000.0 1.219000003730 3 16 69 17100000.0 1.22400000 18000000.0 1.22000000 18500000.0 1.221000003730 3 16 70 19000000.0 1.21600000 19700000.0 1.19700000 20000000.0 1.190000003730 3 16 71 3730 3 0 72 3.70850E+4 8.41824E+1 0 1 0 03730 3107 73 2.93000E+2 9.91000E+5 0 0 1 123730 3107 74 12 2 3730 3107 75 100000.000 0.0 9500000.00 0.0 10000000.0 .0004000003730 3107 76 12000000.0 .002400000 13000000.0 .004000000 14000000.0 .0050000003730 3107 77 15000000.0 .007000000 16000000.0 .008000000 17000000.0 .0085000003730 3107 78 18000000.0 .008500000 19000000.0 .008000000 20000000.0 .0070000003730 3107 79 3730 3 0 80 3730 0 0 81 0 0 0 82 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0