IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 6.01420E+4 1.40689E+2 0 0 1 16030 1451 1 0.0 0.0 0 0 0 06030 1451 2 0.0 0.0 0 0 48 26030 1451 3 60-Nd-142 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.6030 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 6030 1451 5 IDENTIFIER=INDL 6030 REV1 6030 1451 6 FORMAT= ENDF/B-5 6030 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 6030 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 6030 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 6030 1451 10 TEXT= 6030 1451 11 60-ND-142(N,2N)60-ND-141 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 6030 1451 12 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 6030 1451 13 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 6030 1451 14 OBNINSK,USSR). 6030 1451 15 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 6030 1451 16 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 6030 1451 17 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 6030 1451 18 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 6030 1451 19 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 6030 1451 20 KONSTANTY,32(1),PAGE 105,1979 6030 1451 21 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 6030 1451 22 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 6030 1451 23 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 6030 1451 24 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 6030 1451 25 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 6030 1451 26 YAD. KOSTANTY 3,(42),P.60,(1981) 6030 1451 27 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.6030 1451 28 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 6030 1451 29 REACTION | V.2,P.271,IAEA,VIENNA) 6030 1451 30 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 6030 1451 31 -------------|-------------|---------------|------------------ 6030 1451 32 60-ND-142(N,2N) | 0.627 | 0.530 | 0.795 6030 1451 33 ***************** Program LINEAR (VERSION 2002-1) ***************6030 1451 34 For All Data Greater than 1.0000E-10 barns in Absolute Value 6030 1451 35 Data Linearized to Within an Accuracy of .100000000 per-cent 6030 1451 36 ***************** Program FIXUP (Version 2002-1) ****************6030 1451 37 Corrected ZA/AWR in All Sections-----------------------------Yes 6030 1451 38 Corrected Thresholds-----------------------------------------Yes 6030 1451 39 Extended Cross Sections to 20 MeV----------------------------No 6030 1451 40 Allow Cross Section Deletion---------------------------------No 6030 1451 41 Allow Cross Section Reconstruction---------------------------No 6030 1451 42 Make All Cross Sections Non-Negative-------------------------Yes 6030 1451 43 Delete Energies Not in Ascending Order-----------------------Yes 6030 1451 44 Deleted Duplicate Points-------------------------------------Yes 6030 1451 45 Check for Ascending MAT/MF/MT Order--------------------------Yes 6030 1451 46 Check for Legal MF/MT Numbers--------------------------------Yes 6030 1451 47 Allow Creation of Missing Sections---------------------------No 6030 1451 48 Allow Insertion of Energy Points-----------------------------No 6030 1451 49 Create Uniform Energy Grid-----------------------------------No 6030 1451 50 Delete Section if Cross Section =0 at All Energies-----------Yes 6030 1451 51 1 451 53 16030 1451 52 3 16 17 16030 1451 53 6030 1 0 54 6030 0 0 55 6.01420E+4 1.40689E+2 0 1 0 06030 3 16 56 2.93000E+2-9.81000E+6 0 0 1 426030 3 16 57 42 2 6030 3 16 58 9880000.00 0.0 10000000.0 0.0 10100000.0 .0291700006030 3 16 59 10200000.0 .060200000 10300000.0 .093070000 10400000.0 .1278000006030 3 16 60 10500000.0 .164400000 10600000.0 .202800000 10700000.0 .2431000006030 3 16 61 10800000.0 .285200000 10900000.0 .329200000 11000000.0 .3750000006030 3 16 62 11100000.0 .435900000 11200000.0 .495800000 11400000.0 .6122000006030 3 16 63 11600000.0 .724200000 11800000.0 .831800000 12000000.0 .9350000006030 3 16 64 12100000.0 .989200000 12300000.0 1.09100000 12400000.0 1.140000006030 3 16 65 12600000.0 1.23000000 12800000.0 1.31100000 13000000.0 1.385000006030 3 16 66 13300000.0 1.47100000 13600000.0 1.54600000 13900000.0 1.611000006030 3 16 67 14100000.0 1.64600000 14500000.0 1.70300000 14900000.0 1.750000006030 3 16 68 15200000.0 1.77500000 16000000.0 1.82500000 16700000.0 1.859000006030 3 16 69 17400000.0 1.88600000 17800000.0 1.89200000 18200000.0 1.893000006030 3 16 70 18500000.0 1.88700000 18800000.0 1.87000000 19100000.0 1.845000006030 3 16 71 19400000.0 1.80900000 19700000.0 1.76300000 20000000.0 1.705000006030 3 16 72 6030 3 0 73 6030 0 0 74 0 0 0 75 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0