IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 7.01400E+3 1.38828E+1 0 0 1 1 730 1451 1 0.0 0.0 0 0 0 0 730 1451 2 0.0 0.0 0 0 50 2 730 1451 3 7-N - 14 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL. 730 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 730 1451 5 IDENTIFIER=INDL 0730 REV1 730 1451 6 FORMAT= ENDF/B-5 730 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 730 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 730 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 730 1451 10 TEXT= 730 1451 11 7-N-14(N,2N)7-N-13 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 730 1451 12 7-N-14(N,A)5-B-11 EN.REGION UP TO 20.MEV IN STEPS OF 100.KEV 730 1451 13 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 730 1451 14 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 730 1451 15 OBNINSK,USSR). 730 1451 16 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 730 1451 17 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 730 1451 18 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 730 1451 19 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 730 1451 20 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 730 1451 21 KONSTANTY,32(1),PAGE 105,1979 730 1451 22 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 730 1451 23 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 730 1451 24 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 730 1451 25 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 730 1451 26 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 730 1451 27 YAD. KOSTANTY 3,(42),P.60,(1981) 730 1451 28 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP. 730 1451 29 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 730 1451 30 REACTION | V.2,P.271,IAEA,VIENNA) 730 1451 31 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 730 1451 32 -------------|-------------|---------------|------------------ 730 1451 33 7-N-14(N,2N) | 0.94E-03 | 0.77E-03 | 1.3E-02 730 1451 34 7-N-14(N,A) | 91.0 | 90.2 | 85.0 730 1451 35 ***************** Program LINEAR (VERSION 2002-1) *************** 730 1451 36 For All Data Greater than 1.0000E-10 barns in Absolute Value 730 1451 37 Data Linearized to Within an Accuracy of .100000000 per-cent 730 1451 38 ***************** Program FIXUP (Version 2002-1) **************** 730 1451 39 Corrected ZA/AWR in All Sections-----------------------------Yes 730 1451 40 Corrected Thresholds-----------------------------------------Yes 730 1451 41 Extended Cross Sections to 20 MeV----------------------------No 730 1451 42 Allow Cross Section Deletion---------------------------------No 730 1451 43 Allow Cross Section Reconstruction---------------------------No 730 1451 44 Make All Cross Sections Non-Negative-------------------------Yes 730 1451 45 Delete Energies Not in Ascending Order-----------------------Yes 730 1451 46 Deleted Duplicate Points-------------------------------------Yes 730 1451 47 Check for Ascending MAT/MF/MT Order--------------------------Yes 730 1451 48 Check for Legal MF/MT Numbers--------------------------------Yes 730 1451 49 Allow Creation of Missing Sections---------------------------No 730 1451 50 Allow Insertion of Energy Points-----------------------------No 730 1451 51 Create Uniform Energy Grid-----------------------------------No 730 1451 52 Delete Section if Cross Section =0 at All Energies-----------Yes 730 1451 53 1 451 55 1 730 1451 54 3 16 15 1 730 1451 55 730 1 0 56 730 0 0 57 7.01400E+3 1.38828E+1 0 0 0 0 730 3 16 58 2.93000E+2-1.05500E+7 0 0 1 36 730 3 16 59 36 2 730 3 16 60 11310000.0 0.0 11500000.0 0.0 11600000.0 .000100000 730 3 16 61 11800000.0 .000400000 11900000.0 .000650000 12000000.0 .000800000 730 3 16 62 12100000.0 .001007000 12200000.0 .001220000 12300000.0 .001437000 730 3 16 63 12400000.0 .001660000 12500000.0 .001887000 12700000.0 .002357000 730 3 16 64 12900000.0 .002847000 13000000.0 .003100000 13200000.0 .003692000 730 3 16 65 13400000.0 .004268000 13700000.0 .005102000 14000000.0 .005900000 730 3 16 66 14200000.0 .006476000 14400000.0 .007004000 14600000.0 .007484000 730 3 16 67 14800000.0 .007916000 15000000.0 .008300000 15400000.0 .008828000 730 3 16 68 15800000.0 .009292000 16300000.0 .009803000 16600000.0 .010050000 730 3 16 69 16900000.0 .010250000 17200000.0 .010390000 17600000.0 .010490000 730 3 16 70 17900000.0 .010510000 18100000.0 .010470000 18500000.0 .010340000 730 3 16 71 19100000.0 .010040000 19500000.0 .009787000 20000000.0 .009400000 730 3 16 72 730 3 0 73 730 0 0 74 0 0 0 75 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0