IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 5.91410E+4 1.39697E+2 0 0 1 15930 1451 1 0.0 0.0 0 0 0 05930 1451 2 0.0 0.0 0 0 48 25930 1451 3 59-Pr-141 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.5930 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 5930 1451 5 IDENTIFIER=INDL 5930 REV1 5930 1451 6 FORMAT= ENDF/B-5 5930 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 5930 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 5930 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 5930 1451 10 TEXT= 5930 1451 11 59-PR-141(N,2N)59-PR-140 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 5930 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 5930 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 5930 1451 14 OBNINSK,USSR). 5930 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 5930 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 5930 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 5930 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 5930 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 5930 1451 20 KONSTANTY,32(1),PAGE 105,1979 5930 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 5930 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 5930 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 5930 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 5930 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 5930 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 5930 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.5930 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 5930 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 5930 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 5930 1451 31 -------------|-------------|---------------|------------------ 5930 1451 32 59-PR-141(N,2N) | 1.10 | 0.95 | 1.34 5930 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************5930 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 5930 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 5930 1451 36 ***************** Program FIXUP (Version 2002-1) ****************5930 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 5930 1451 38 Corrected Thresholds-----------------------------------------Yes 5930 1451 39 Extended Cross Sections to 20 MeV----------------------------No 5930 1451 40 Allow Cross Section Deletion---------------------------------No 5930 1451 41 Allow Cross Section Reconstruction---------------------------No 5930 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 5930 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 5930 1451 44 Deleted Duplicate Points-------------------------------------Yes 5930 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 5930 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 5930 1451 47 Allow Creation of Missing Sections---------------------------No 5930 1451 48 Allow Insertion of Energy Points-----------------------------No 5930 1451 49 Create Uniform Energy Grid-----------------------------------No 5930 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 5930 1451 51 1 451 53 15930 1451 52 3 16 18 15930 1451 53 5930 1 0 54 5930 0 0 55 5.91410E+4 1.39697E+2 0 1 0 05930 3 16 56 2.93000E+2-9.40000E+6 0 0 1 435930 3 16 57 43 2 5930 3 16 58 9467288.49 0.0 9600000.00 0.0 9700000.00 .0450000005930 3 16 59 9800000.00 .125000000 9900000.00 .200000000 10000000.0 .2600000005930 3 16 60 10100000.0 .331300000 10200000.0 .400400000 10300000.0 .4671000005930 3 16 61 10400000.0 .531600000 10500000.0 .593700000 10600000.0 .6536000005930 3 16 62 10700000.0 .711100000 10800000.0 .766400000 10900000.0 .8193000005930 3 16 63 11000000.0 .870000000 11200000.0 .958800000 11300000.0 1.001000005930 3 16 64 11500000.0 1.08000000 11700000.0 1.15300000 11900000.0 1.219000005930 3 16 65 12000000.0 1.25000000 12200000.0 1.30000000 12500000.0 1.370000005930 3 16 66 12800000.0 1.43200000 13000000.0 1.47000000 13400000.0 1.532000005930 3 16 67 13800000.0 1.58600000 14200000.0 1.63100000 14700000.0 1.677000005930 3 16 68 15000000.0 1.70000000 16000000.0 1.75000000 16500000.0 1.779000005930 3 16 69 17300000.0 1.80400000 17500000.0 1.80500000 17800000.0 1.799000005930 3 16 70 18100000.0 1.78400000 18500000.0 1.75100000 18800000.0 1.714000005930 3 16 71 19000000.0 1.68500000 19400000.0 1.60800000 19800000.0 1.521000005930 3 16 72 20000000.0 1.47500000 5930 3 16 73 5930 3 0 74 5930 0 0 75 0 0 0 76 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0