IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 5.01120E+4 1.10943E+2 0 0 1 15030 1451 1 0.0 0.0 0 0 0 05030 1451 2 0.0 0.0 0 0 48 25030 1451 3 50-Sn-112 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.5030 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 5030 1451 5 IDENTIFIER=INDL 5030 REV1 5030 1451 6 FORMAT= ENDF/B-5 5030 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 5030 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 5030 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 5030 1451 10 TEXT= 5030 1451 11 50-SN-112(N,2N)50-SN-111 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 5030 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 5030 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 5030 1451 14 OBNINSK,USSR). 5030 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 5030 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 5030 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 5030 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 5030 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 5030 1451 20 KONSTANTY,32(1),PAGE 105,1979 5030 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 5030 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 5030 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 5030 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 5030 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 5030 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 5030 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.5030 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 5030 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 5030 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 5030 1451 31 -------------|-------------|---------------|------------------ 5030 1451 32 50-SN-112(N,2N) | 0.235 | 0.194 | 0.315 5030 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************5030 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 5030 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 5030 1451 36 ***************** Program FIXUP (Version 2002-1) ****************5030 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 5030 1451 38 Corrected Thresholds-----------------------------------------Yes 5030 1451 39 Extended Cross Sections to 20 MeV----------------------------No 5030 1451 40 Allow Cross Section Deletion---------------------------------No 5030 1451 41 Allow Cross Section Reconstruction---------------------------No 5030 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 5030 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 5030 1451 44 Deleted Duplicate Points-------------------------------------Yes 5030 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 5030 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 5030 1451 47 Allow Creation of Missing Sections---------------------------No 5030 1451 48 Allow Insertion of Energy Points-----------------------------No 5030 1451 49 Create Uniform Energy Grid-----------------------------------No 5030 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 5030 1451 51 1 451 53 15030 1451 52 3 16 17 15030 1451 53 5030 1 0 54 5030 0 0 55 5.01120E+4 1.10943E+2 0 1 0 05030 3 16 56 2.93000E+2-1.08000E+7 0 0 1 405030 3 16 57 40 2 5030 3 16 58 10897347.3 0.0 11200000.0 0.0 11300000.0 .0500000005030 3 16 59 11400000.0 .090000000 11500000.0 .140000000 11600000.0 .1800000005030 3 16 60 11700000.0 .240000000 11800000.0 .290000000 12000000.0 .3800000005030 3 16 61 12100000.0 .430200000 12200000.0 .478800000 12300000.0 .5258000005030 3 16 62 12400000.0 .571200000 12500000.0 .615000000 12600000.0 .6572000005030 3 16 63 12700000.0 .697800000 12800000.0 .736800000 12900000.0 .7742000005030 3 16 64 13000000.0 .810000000 13200000.0 .872000000 13400000.0 .9300000005030 3 16 65 13600000.0 .984000000 13800000.0 1.03400000 14200000.0 1.124000005030 3 16 66 14400000.0 1.16200000 14600000.0 1.19600000 14800000.0 1.226000005030 3 16 67 15000000.0 1.25000000 15300000.0 1.27100000 15700000.0 1.291000005030 3 16 68 16000000.0 1.30000000 16400000.0 1.30200000 16800000.0 1.296000005030 3 16 69 17000000.0 1.29000000 18000000.0 1.23000000 18500000.0 1.209000005030 3 16 70 19200000.0 1.16900000 19600000.0 1.13900000 19900000.0 1.111000005030 3 16 71 20000000.0 1.05000000 5030 3 16 72 5030 3 0 73 5030 0 0 74 0 0 0 75 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0