IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 8.32090E+4 2.07185E+2 0 0 1 18330 1451 1 0.0 0.0 0 0 0 08330 1451 2 0.0 0.0 0 0 68 38330 1451 3 83-Bi-209 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.8330 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 8330 1451 5 IDENTIFIER=INDL 8330 REV1 8330 1451 6 FORMAT= ENDF/B-5 8330 1451 7 =============================================================== 8330 1451 8 ======================== For MF = 16 ======================== 8330 1451 9 8330 1451 10 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 8330 1451 11 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 8330 1451 12 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 8330 1451 13 TEXT= 8330 1451 14 83-BI-209(N,2N)83-BI-208 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 8330 1451 15 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 8330 1451 16 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 8330 1451 17 OBNINSK,USSR). 8330 1451 18 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 8330 1451 19 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 8330 1451 20 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 8330 1451 21 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 8330 1451 22 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 8330 1451 23 KONSTANTY,32(1),PAGE 105,1979 8330 1451 24 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 8330 1451 25 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 8330 1451 26 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 8330 1451 27 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 8330 1451 28 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 8330 1451 29 YAD. KOSTANTY 3,(42),P.60,(1981) 8330 1451 30 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.8330 1451 31 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 8330 1451 32 REACTION | V.2,P.271,IAEA,VIENNA) 8330 1451 33 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 8330 1451 34 -------------|-------------|---------------|------------------ 8330 1451 35 83-BI-209(N,2N)| 5.92 | 5.27 | 6.5 8330 1451 36 8330 1451 37 =============================================================== 8330 1451 38 ======================== For MF = 103 ======================== 8330 1451 39 0.83209E 05 0.2072E 03 0 0 1 18330 1451 40 0.0 0.0 0 0 0 08330 1451 41 0.0 0.0 0 0 9 28330 1451 42 83-Bi-209 1USALRL EVAL- 82 8330 1451 43 8330 1451 44 IDENTIFIER=ENDL 8335 8330 1451 45 FORMAT= ENDF/B-5 8330 1451 46 HISTORY= 840315 DATA WERE CONVERTED IN ENDF/B-5 FORMAT BY NDS 8330 1451 47 8330 1451 48 TEXT= 8330 1451 49 THIS EVALUATED CROSS-SECTION WAS TAKEN FROM LIVERMORE ACTIVATION 8330 1451 50 LIBRARY 8330 1451 51 8330 1451 52 =============================================================== 8330 1451 53 ***************** Program LINEAR (VERSION 2002-1) ***************8330 1451 54 For All Data Greater than 1.0000E-10 barns in Absolute Value 8330 1451 55 Data Linearized to Within an Accuracy of .100000000 per-cent 8330 1451 56 ***************** Program FIXUP (Version 2002-1) ****************8330 1451 57 Corrected ZA/AWR in All Sections-----------------------------Yes 8330 1451 58 Corrected Thresholds-----------------------------------------Yes 8330 1451 59 Extended Cross Sections to 20 MeV----------------------------No 8330 1451 60 Allow Cross Section Deletion---------------------------------No 8330 1451 61 Allow Cross Section Reconstruction---------------------------No 8330 1451 62 Make All Cross Sections Non-Negative-------------------------Yes 8330 1451 63 Delete Energies Not in Ascending Order-----------------------Yes 8330 1451 64 Deleted Duplicate Points-------------------------------------Yes 8330 1451 65 Check for Ascending MAT/MF/MT Order--------------------------Yes 8330 1451 66 Check for Legal MF/MT Numbers--------------------------------Yes 8330 1451 67 Allow Creation of Missing Sections---------------------------No 8330 1451 68 Allow Insertion of Energy Points-----------------------------No 8330 1451 69 Create Uniform Energy Grid-----------------------------------No 8330 1451 70 Delete Section if Cross Section =0 at All Energies-----------Yes 8330 1451 71 1 451 74 18330 1451 72 3 16 19 18330 1451 73 3 103 7 18330 1451 74 8330 1 0 75 8330 0 0 76 8.32090E+4 2.07185E+2 0 1 0 08330 3 16 77 2.93000E+2-7.45000E+6 0 0 1 478330 3 16 78 47 2 8330 3 16 79 7485958.20 0.0 7700000.00 0.0 7800000.00 .0500000008330 3 16 80 7900000.00 .110000000 8000000.00 .160000000 8100000.00 .2541000008330 3 16 81 8200000.00 .345400000 8300000.00 .433900000 8400000.00 .5196000008330 3 16 82 8500000.00 .602500000 8600000.00 .682600000 8700000.00 .7599000008330 3 16 83 8800000.00 .834400000 8900000.00 .906100000 9000000.00 .9750000008330 3 16 84 9600000.00 1.29900000 10000000.0 1.51000000 10400000.0 1.670000008330 3 16 85 10600000.0 1.74000000 11100000.0 1.89000000 11200000.0 1.925000008330 3 16 86 11300000.0 1.94500000 11400000.0 1.97000000 11900000.0 2.075000008330 3 16 87 12000000.0 2.10000000 12600000.0 2.16600000 13100000.0 2.207000008330 3 16 88 13700000.0 2.23900000 14400000.0 2.26000000 14800000.0 2.262000008330 3 16 89 15000000.0 2.26000000 15300000.0 2.26200000 15700000.0 2.246000008330 3 16 90 16200000.0 2.20400000 16400000.0 2.18000000 16600000.0 2.146000008330 3 16 91 16900000.0 2.07700000 17000000.0 2.05000000 17700000.0 1.767000008330 3 16 92 18000000.0 1.65000000 18300000.0 1.52700000 18600000.0 1.413000008330 3 16 93 18900000.0 1.30800000 19100000.0 1.24400000 19500000.0 1.128000008330 3 16 94 19900000.0 1.02400000 20000000.0 1.00000000 8330 3 16 95 8330 3 0 96 8.32090E+4 2.07185E+2 0 0 0 08330 3103 97 2.93000E+2 1.30000E+5 0 0 1 128330 3103 98 12 2 8330 3103 99 9900000.00 0.0 10000000.0 1.00000E-7 11000000.0 .0001600008330 3103 100 12000000.0 .000240000 13000000.0 .000490000 14000000.0 .0007200008330 3103 101 15000000.0 .000890000 16000000.0 .001050000 17000000.0 .0014600008330 3103 102 18000000.0 .001900000 19000000.0 .002430000 20000000.0 .0025100008330 3103 103 8330 3 0 104 8330 0 0 105 0 0 0 106 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0