IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 3.50810E+4 8.02212E+1 0 0 1 13540 1451 1 0.0 0.0 0 0 0 03540 1451 2 0.0 0.0 0 0 50 33540 1451 3 35-Br- 81 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.3540 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 3540 1451 5 IDENTIFIER=INDL 3540 REV1 3540 1451 6 FORMAT= ENDF/B-5 3540 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 3540 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 3540 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 3540 1451 10 TEXT= 3540 1451 11 35-BR-81(N,2N)35-BR-80 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 3540 1451 12 35-BR-81(N,2N)35-BR-80M EN.REG.UP TO 20.MEV IN 100.KEV STEPS 3540 1451 13 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 3540 1451 14 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 3540 1451 15 OBNINSK,USSR). 3540 1451 16 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 3540 1451 17 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 3540 1451 18 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 3540 1451 19 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 3540 1451 20 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 3540 1451 21 KONSTANTY,32(1),PAGE 105,1979 3540 1451 22 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 3540 1451 23 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 3540 1451 24 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 3540 1451 25 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 3540 1451 26 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 3540 1451 27 YAD. KOSTANTY 3,(42),P.60,(1981) 3540 1451 28 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.3540 1451 29 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 3540 1451 30 REACTION | V.2,P.271,IAEA,VIENNA) 3540 1451 31 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 3540 1451 32 -------------|-------------|---------------|------------------ 3540 1451 33 35-BR-81(N,2N) | 0.288 | 0.242 | 0.374 3540 1451 34 35-BR-81(N,2N)M| 0.168 | 0.140 | 0.221 3540 1451 35 ***************** Program LINEAR (VERSION 2002-1) ***************3540 1451 36 For All Data Greater than 1.0000E-10 barns in Absolute Value 3540 1451 37 Data Linearized to Within an Accuracy of .100000000 per-cent 3540 1451 38 ***************** Program FIXUP (Version 2002-1) ****************3540 1451 39 Corrected ZA/AWR in All Sections-----------------------------Yes 3540 1451 40 Corrected Thresholds-----------------------------------------Yes 3540 1451 41 Extended Cross Sections to 20 MeV----------------------------No 3540 1451 42 Allow Cross Section Deletion---------------------------------No 3540 1451 43 Allow Cross Section Reconstruction---------------------------No 3540 1451 44 Make All Cross Sections Non-Negative-------------------------Yes 3540 1451 45 Delete Energies Not in Ascending Order-----------------------Yes 3540 1451 46 Deleted Duplicate Points-------------------------------------Yes 3540 1451 47 Check for Ascending MAT/MF/MT Order--------------------------Yes 3540 1451 48 Check for Legal MF/MT Numbers--------------------------------Yes 3540 1451 49 Allow Creation of Missing Sections---------------------------No 3540 1451 50 Allow Insertion of Energy Points-----------------------------No 3540 1451 51 Create Uniform Energy Grid-----------------------------------No 3540 1451 52 Delete Section if Cross Section =0 at All Energies-----------Yes 3540 1451 53 1 451 56 13540 1451 54 3 16 14 13540 1451 55 3 26 15 13540 1451 56 3540 1 0 57 3540 0 0 58 3.50810E+4 8.02212E+1 0 1 0 03540 3 16 59 2.93000E+2-1.01600E+7 0 0 1 313540 3 16 60 31 2 3540 3 16 61 10286649.8 0.0 10600000.0 .025000000 10700000.0 .0600000003540 3 16 62 11000000.0 .150000000 11200000.0 .211600000 11500000.0 .3025000003540 3 16 63 11800000.0 .391600000 12000000.0 .450000000 12200000.0 .5100000003540 3 16 64 12500000.0 .596200000 12800000.0 .678000000 13000000.0 .7300000003540 3 16 65 13200000.0 .784800000 13400000.0 .835200000 13600000.0 .8812000003540 3 16 66 13800000.0 .922800000 14000000.0 .960000000 14300000.0 1.001000003540 3 16 67 14700000.0 1.04900000 15100000.0 1.08900000 15500000.0 1.120000003540 3 16 68 16000000.0 1.15000000 16700000.0 1.17300000 17300000.0 1.187000003540 3 16 69 17800000.0 1.19400000 18300000.0 1.19800000 18500000.0 1.198000003540 3 16 70 18800000.0 1.19500000 19100000.0 1.18600000 19500000.0 1.169000003540 3 16 71 20000000.0 1.14000000 3540 3 16 72 3540 3 0 73 3.50810E+4 8.02212E+1 0 1 0 03540 3 26 74 2.93000E+2-1.02500E+7 0 0 1 363540 3 26 75 36 2 3540 3 26 76 10377771.7 0.0 10900000.0 0.0 11000000.0 .0070000003540 3 26 77 11100000.0 .042380000 11200000.0 .076640000 11300000.0 .1098000003540 3 26 78 11400000.0 .141800000 11500000.0 .172600000 11600000.0 .2024000003540 3 26 79 11700000.0 .231000000 11800000.0 .258400000 11900000.0 .2848000003540 3 26 80 12000000.0 .310000000 12200000.0 .353200000 12400000.0 .3938000003540 3 26 81 12600000.0 .431800000 12800000.0 .467200000 13000000.0 .5000000003540 3 26 82 13200000.0 .529500000 13400000.0 .556700000 13700000.0 .5934000003540 3 26 83 14000000.0 .625000000 14300000.0 .649300000 14700000.0 .6769000003540 3 26 84 15000000.0 .694000000 15500000.0 .714500000 16000000.0 .7290000003540 3 26 85 16500000.0 .736500000 17300000.0 .742200000 17400000.0 .7422000003540 3 26 86 17800000.0 .738800000 18000000.0 .735000000 18500000.0 .7175000003540 3 26 87 19000000.0 .695000000 19500000.0 .666900000 20000000.0 .6350000003540 3 26 88 3540 3 0 89 3540 0 0 90 0 0 0 91 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0