IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 6.01480E+4 1.46638E+2 0 0 1 16050 1451 1 0.0 0.0 0 0 0 06050 1451 2 0.0 0.0 0 0 50 26050 1451 3 60-Nd-148 4CCPFEI EVAL-NOV78 V.M.BYCHKOV,K.I.ZOLOTAREV ET AL.6050 1451 4 YK-3,(42),60 ,8109 DIST-JAN81 820212 6050 1451 5 IDENTIFIER=INDL 6050 REV1 6050 1451 6 FORMAT= ENDF/B-5 6050 1451 7 HISTORY= 8106 RECEIVED AT IAEA IN INTERNAL FORMAT 6050 1451 8 820212 DATA WERE CONVERTED FROM INTERNAL FORMAT TO 6050 1451 9 ENDF/B-5 FORMAT BY NDS IAEA.APPROVED BY AUTHOR. VP. 6050 1451 10 840502 CORRECTED FOR EN=7 - 15 MEV BY VP. 6050 1451 11 6050 1451 12 TEXT= 6050 1451 13 60-ND-148(N,2N)60-ND-147 EN.REG.UP TO 20.MEV IN 100.KEV STEPS 6050 1451 14 THESE EVALUATED DATA ARE KNOWN AS BOSPOR-80 LIBRARY(THE LIBRARY 6050 1451 15 OF THRESHOLD REACTION CROSS-SECTIONS OF THE NUCLEAR DATA CENTRE, 6050 1451 16 OBNINSK,USSR). 6050 1451 17 THE EVAL.DATA OF BOSPOR-80 LIBRARY WERE OBTAINED AS A RESULT 6050 1451 18 OF CRITICAL ANALYSIS OF ALL THE DATA FROM EXFOR LIBRARY AND 6050 1451 19 CINDA REFERENCES ON THE BASIS OF STATISTICAL AND 6050 1451 20 PRE-EQUILIBRIUM MODELS OF NUCLEAR REACTIONS. 6050 1451 21 FOR A COMPLETE DISCUSSION OF THE EVALUATION METHOD SEE JADERNYE 6050 1451 22 KONSTANTY,32(1),PAGE 105,1979 6050 1451 23 (ENGLISH TRANSLATION INDC(CCP)-147,JUNE 1980). 6050 1451 24 BELOW ARE GIVEN THE VALUES OF EVALUATED CROSS-SECTIONS 6050 1451 25 AVERAGED ON DIFFERENT TYPES OF U-235 NEUTRON FISSION SPECTRA 6050 1451 26 INDUCED BY THERMAL NEUTRONS (IN MBARNS) 6050 1451 27 THESE SPECTRUM AVERAGED VALUES WERE COMPUTED AT FEI AS GIVEN IN 6050 1451 28 YAD. KOSTANTY 3,(42),P.60,(1981) 6050 1451 29 | TYPE OF SPECTRUM (SEE ZIJP W.L.,IN PROC.OF SYMP.6050 1451 30 | ON NUCLEAR DATA IN SC. AND TECHN.,PARIS,1973, 6050 1451 31 REACTION | V.2,P.271,IAEA,VIENNA) 6050 1451 32 | WATT,B.E. |CRANBERG,L. | LEACHMAN,R. 6050 1451 33 -------------|-------------|---------------|------------------ 6050 1451 34 60-ND-148(N,2N) | 6.13 | 5.49 | 6.64 6050 1451 35 ***************** Program LINEAR (VERSION 2002-1) ***************6050 1451 36 For All Data Greater than 1.0000E-10 barns in Absolute Value 6050 1451 37 Data Linearized to Within an Accuracy of .100000000 per-cent 6050 1451 38 ***************** Program FIXUP (Version 2002-1) ****************6050 1451 39 Corrected ZA/AWR in All Sections-----------------------------Yes 6050 1451 40 Corrected Thresholds-----------------------------------------Yes 6050 1451 41 Extended Cross Sections to 20 MeV----------------------------No 6050 1451 42 Allow Cross Section Deletion---------------------------------No 6050 1451 43 Allow Cross Section Reconstruction---------------------------No 6050 1451 44 Make All Cross Sections Non-Negative-------------------------Yes 6050 1451 45 Delete Energies Not in Ascending Order-----------------------Yes 6050 1451 46 Deleted Duplicate Points-------------------------------------Yes 6050 1451 47 Check for Ascending MAT/MF/MT Order--------------------------Yes 6050 1451 48 Check for Legal MF/MT Numbers--------------------------------Yes 6050 1451 49 Allow Creation of Missing Sections---------------------------No 6050 1451 50 Allow Insertion of Energy Points-----------------------------No 6050 1451 51 Create Uniform Energy Grid-----------------------------------No 6050 1451 52 Delete Section if Cross Section =0 at All Energies-----------Yes 6050 1451 53 1 451 55 16050 1451 54 3 16 18 16050 1451 55 6050 1 0 56 6050 0 0 57 6.01480E+4 1.46638E+2 0 1 0 06050 3 16 58 2.93000E+2-7.32000E+6 0 0 1 456050 3 16 59 45 2 6050 3 16 60 7370000.00 0.0 7600000.00 0.0 7700000.00 .0100000006050 3 16 61 7800000.00 .101000000 7900000.00 .193000000 8000000.00 .2730000006050 3 16 62 8100000.00 .360000000 8200000.00 .443900000 8300000.00 .5229000006050 3 16 63 8400000.00 .599100000 8500000.00 .671700000 8600000.00 .7408000006050 3 16 64 8700000.00 .806300000 8800000.00 .868300000 8900000.00 .9264000006050 3 16 65 9000000.00 .981600000 9100000.00 1.02500000 9300000.00 1.106000006050 3 16 66 9400000.00 1.12600000 9500000.00 1.18100000 9600000.00 1.214000006050 3 16 67 9700000.00 1.22900000 9800000.00 1.27900000 10000000.0 1.336000006050 3 16 68 10300000.0 1.39900000 10600000.0 1.45500000 10900000.0 1.503000006050 3 16 69 11100000.0 1.53000000 11500000.0 1.57400000 11900000.0 1.611000006050 3 16 70 12300000.0 1.64100000 12700000.0 1.66400000 13700000.0 1.714000006050 3 16 71 13900000.0 1.71900000 14100000.0 1.72100000 14700000.0 1.713000006050 3 16 72 14800000.0 1.71000000 15100000.0 1.67800000 15200000.0 1.660000006050 3 16 73 15400000.0 1.63600000 15600000.0 1.59400000 16100000.0 1.500000006050 3 16 74 17200000.0 1.31000000 19800000.0 .879100000 20000000.0 .8470000006050 3 16 75 6050 3 0 76 6050 0 0 77 0 0 0 78 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0