IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 7.31810E+4 1.79394E+2 0 0 1 17330 1451 1 0.0 0.0 0 0 0 07330 1451 2 0.0 0.0 0 0 52 37330 1451 3 73-Ta-181 4CCPFEI EVAL-NOV78 V.M.BYCHKOV ET AL.L.ADAMSKI ET 7330 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 7330 1451 5 IDENTIFIER=INDL 7330 REV1 7330 1451 6 FORMAT= ENDF/B-5 7330 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 7330 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 7330 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 7330 1451 10 TEXT= 7330 1451 11 73-TA-181(N,2N)73-TA-180 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 7330 1451 12 73-TA-181(N,2N)73-TA-180M EN.REG.UP TO 20.MEV IN 100.KEV STEPS 7330 1451 13 73-TA-181(N,P)72-HF-181 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 7330 1451 14 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 7330 1451 15 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 7330 1451 16 OBNINSK,USSR). 7330 1451 17 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 7330 1451 18 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 7330 1451 19 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 7330 1451 20 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 7330 1451 21 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 7330 1451 22 KONSTANTY,32(1),PAGE 105,1979 7330 1451 23 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 7330 1451 24 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 7330 1451 25 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 7330 1451 26 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 7330 1451 27 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 7330 1451 28 YAD. KOSTANTY 3,(42),P.60,(1981) 7330 1451 29 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.7330 1451 30 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 7330 1451 31 REACTION | V.2,P.271,IAEA,VIENNA) 7330 1451 32 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 7330 1451 33 -------------|-------------|---------------|------------------ 7330 1451 34 73-TA-181(N,2N) | 4.96 | 4.41 | 5.49 7330 1451 35 73-TA-181(N,2N)M| 2.63 | 2.34 | 2.91 7330 1451 36 73-TA-181(N,P) | 1.0E-03 | 0.8E-03 | 1.3E-03 7330 1451 37 ***************** Program LINEAR (VERSION 2002-1) ***************7330 1451 38 For All Data Greater than 1.0000E-10 barns in Absolute Value 7330 1451 39 Data Linearized to Within an Accuracy of .100000000 per-cent 7330 1451 40 ***************** Program FIXUP (Version 2002-1) ****************7330 1451 41 Corrected ZA/AWR in All Sections-----------------------------Yes 7330 1451 42 Corrected Thresholds-----------------------------------------Yes 7330 1451 43 Extended Cross Sections to 20 MeV----------------------------No 7330 1451 44 Allow Cross Section Deletion---------------------------------No 7330 1451 45 Allow Cross Section Reconstruction---------------------------No 7330 1451 46 Make All Cross Sections Non-Negative-------------------------Yes 7330 1451 47 Delete Energies Not in Ascending Order-----------------------Yes 7330 1451 48 Deleted Duplicate Points-------------------------------------Yes 7330 1451 49 Check for Ascending MAT/MF/MT Order--------------------------Yes 7330 1451 50 Check for Legal MF/MT Numbers--------------------------------Yes 7330 1451 51 Allow Creation of Missing Sections---------------------------No 7330 1451 52 Allow Insertion of Energy Points-----------------------------No 7330 1451 53 Create Uniform Energy Grid-----------------------------------No 7330 1451 54 Delete Section if Cross Section =0 at All Energies-----------Yes 7330 1451 55 1 451 58 17330 1451 56 3 26 8 17330 1451 57 3 103 19 17330 1451 58 7330 1 0 59 7330 0 0 60 7.31810E+4 1.79394E+2 0 1 0 07330 3 26 61 2.93000E+2-7.64000E+6 0 0 1 147330 3 26 62 14 2 7330 3 26 63 7683000.00 0.0 8000000.00 0.0 8250000.00 .0176000007330 3 26 64 8500000.00 .128000000 8750000.00 .301000000 9250000.00 .7180000007330 3 26 65 10250000.0 1.08500000 11250000.0 1.32200000 12250000.0 1.375000007330 3 26 66 13250000.0 1.35200000 14250000.0 1.28000000 16250000.0 1.062000007330 3 26 67 18250000.0 .503000000 20000000.0 .365000000 7330 3 26 68 7330 3 0 69 7.31810E+4 1.79394E+2 0 1 0 07330 3103 70 2.93000E+2-2.39000E+5 0 0 1 477330 3103 71 47 2 7330 3103 72 240332.263 0.0 10000000.0 0.0 10100000.0 4.32500E-57330 3103 73 10200000.0 8.80000E-5 10300000.0 .000134200 10400000.0 .0001820007330 3103 74 10500000.0 .000231200 10600000.0 .000282000 10700000.0 .0003342007330 3103 75 10800000.0 .000388000 10900000.0 .000443200 11000000.0 .0005000007330 3103 76 11100000.0 .000549200 11200000.0 .000602000 11300000.0 .0006582007330 3103 77 11400000.0 .000718000 11500000.0 .000781200 11600000.0 .0008480007330 3103 78 11700000.0 .000918200 11800000.0 .000992000 11900000.0 .0010690007330 3103 79 12100000.0 .001230000 12200000.0 .001314000 12300000.0 .0014030007330 3103 80 12400000.0 .001496000 12500000.0 .001594000 12600000.0 .0016960007330 3103 81 12700000.0 .001803000 12800000.0 .001914000 13000000.0 .0021500007330 3103 82 13300000.0 .002564000 13600000.0 .002996000 13900000.0 .0034460007330 3103 83 14000000.0 .003600000 14300000.0 .004116000 14700000.0 .0047760007330 3103 84 15300000.0 .005722000 15600000.0 .006162000 15900000.0 .0065710007330 3103 85 16200000.0 .006944000 16600000.0 .007396000 17000000.0 .0078000007330 3103 86 17600000.0 .008298000 18200000.0 .008742000 18800000.0 .0091320007330 3103 87 19300000.0 .009405000 20000000.0 .009750000 7330 3103 88 7330 3 0 89 7330 0 0 90 0 0 0 91 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0