IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 2.90650+ 4 6.43700+ 1 1 0 34 12931 1451 1 0.00000+ 0 0.00000+ 0 0 0 0 62931 1451 2 1.00000+ 0 2.00000+ 7 0 0 10 32931 1451 3 0.00000+ 0 0.00000+ 0 0 0 103 32931 1451 4 29-Cu- 65 ORNL EVAL-NOV89 HETRICK,FU,LARSON 2931 1451 5 ORNL/TM-9083,ENDF-337 DIST-FEB91 910201 2931 1451 6 ----IRDF-90 MATERIAL 2931 2931 1451 7 -----INCIDENT NEUTRON DATA 2931 1451 8 ------ENDF-6 FORMAT 2931 1451 9 ******************************************************************2931 1451 10 ORNL/TM-9083,ENDF-337 DIST-NOV89 891109 2931 1451 11 ENDF/B-VI MATERIAL 2931 2931 1451 12 *****************EXTRACT FOR SPECIAL PURPOSE FILE*****************2931 1451 13 DOSIMETRY 2931 1451 14 ******************************************************************2931 1451 15 THIS WORK EMPLOYED SEVERAL NUCLEAR MODEL CODES INCLUDING THE 2931 1451 16 OPTICAL-MODEL CODE GENOA (1), THE DISTORTED WAVE BORN 2931 1451 17 APPROXIMATION (DWBA) PROGRAM DWUCK (2), AND THE HAUSER-FESHBACH 2931 1451 18 CODE TNG (3,4). THE TNG CODE PROVIDES ENERGY AND ANGULAR 2931 1451 19 DISTRIBUTIONS OF PARTICLES EMITTED IN THE COMPOUND AND PRE- 2931 1451 20 COMPOUND REACTIONS, ENSURES CONSISTENCY AMONG ALL REACTIONS, AND 2931 1451 21 MAINTAINS ENERGY BALANCE. DETAILS PERTINENT TO THE CONTENTS OF 2931 1451 22 THIS EVALUATION AND EXTENSIVE COMPARISONS OF CALCULATIONS WITH 2931 1451 23 EXPERIMENTAL DATA CAN BE FOUND IN REFERENCE (5). 2931 1451 24 2931 1451 25 ----- DESCRIPTION OF FILES 2931 1451 26 (MF-MT) 2931 1451 27 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2931 1451 28 2-151 RESONANCE PARAMETERS WERE TAKEN FROM MUGHABGHAB (6). POINT2931 1451 29 WISE RECONSTRUCTION COMPARED WITH DATA (7) SHOWED POORER 2931 1451 30 FIT ABOVE 100 KEV, SO THE RESONANCE REGION WAS CUT OFF AT 2931 1451 31 99.5 KEV. REICH-MOORE PARAMETERS ARE GIVEN. AGREEMENT 2931 1451 32 WITH DATA COULD BE IMPROVED WITH ADDITION OF A BACKGROUND 2931 1451 33 FILE IN 3/1, BUT THIS IN GENERAL GIVES TOO LARGE AN 2931 1451 34 AVERAGE CROSS SECTION, WHEN BINNED IN 10 KEV BINS AND 2931 1451 35 COMPARED WITH THE BINNED DATA. THIS IS PROBABLY DUE TO 2931 1451 36 TOO LARGE AN ESTIMATE OF NEUTRON WIDTHS FOR RESONANCES 2931 1451 37 SEEN ONLY IN CAPTURE AND NOT IN TRANSMISSION. 2931 1451 38 NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2931 1451 39 OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE 2931 1451 40 PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON 2931 1451 41 A FINER ENERGY GRID THAN GIVEN IN 4/2. 2931 1451 42 3-16 (N,2N) CROSS SECTIONS WERE TAKEN FROM THE GLUCS (12) 2931 1451 43 CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL- 2931 1451 44 TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS 2931 1451 45 SECTIONS (13). 2931 1451 46 33-16 (N,2N) COVARIANCES WERE TAKEN FROM THE GLUCS (12) 2931 1451 47 CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL- 2931 1451 48 TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS 2931 1451 49 SECTIONS (13). 2931 1451 50 REFERENCES: 2931 1451 51 (1) F.G. PEREY, COMPUTER CODE GENOA, ORNL, UNPUBLISHED (1967). 2931 1451 52 (2) P.D. KUNZ, "DISTORTED WAVE CODE DWUCK72," UNIV. OF 2931 1451 53 COLORADO, UNPUBLISHED (1972). 2931 1451 54 (3) C.Y. FU, "A CONSISTENT NUCLEAR MODEL FOR COMPOUND AND 2931 1451 55 PRECOMPOUND REACTIONS WITH CONSERVATION OF ANGULAR 2931 1451 56 MOMENTUM," ORNL/TM-7042 (1980). ALSO, 2931 1451 57 C.Y FU, "DEVELOPMENT AND APPLICATION OF MULTI-STEP 2931 1451 58 HAUSER-FESHBACH/PRE-EQUILIBRIUM MODEL THEORY," SYMP. 2931 1451 59 NEUTRON CROSS SECTIONS FROM 10 TO 50 MEV, UPTON, N.Y., 2931 1451 60 MAY 12-14,1980, BNL-NCS-51425, P 675, BROOKHAVEN 2931 1451 61 NATIONAL LAB. 2931 1451 62 (4) K. SHIBATA AND C.Y. FU, "RECENT IMPROVEMENTS OF THE TNG 2931 1451 63 STATISTICAL MODEL CODE," ORNL/TM-10093 (AUGUST, 1986). 2931 1451 64 (5) D.M. HETRICK, C.Y. FU, AND D.C. LARSON, "CALCULATED NEUTRON 2931 1451 65 -INDUCED CROSS SECTIONS FOR 63,65CU FROM 1 TO 20 MEV AND 2931 1451 66 COMPARISONS WITH EXPERIMENT," ORNL/TM-9083,ENDF-337 (1984). 2931 1451 67 (6) S. F. MUGHABGHAB, M. DIVADEENAM, AND N.E. HOLDEN, "NEUTRON 2931 1451 68 CROSS SECTIONS, VOL. 1, NEUTRON RESONANCE PARAMETERS AND 2931 1451 69 THERMAL CROSS SECTIONS, PART A, Z=1-60," ACADEMIC 2931 1451 70 PRESS (1981). 2931 1451 71 (7) M.S. PANDEY, J.B. GARG AND J.A. HARVEY, "NEUTRON TOTAL CROSS 2931 1451 72 SECTIONS AND RESONANCE PARAMETERS OF 63,65CU, I AND II", PHYS2931 1451 73 REV. C15 (1977) 600, AND PRIVATE COMMUNICATION. 2931 1451 74 (8) F.G. PEREY, PRIVATE COMMUNICATION, 1977. 2931 1451 75 (9) D.C. LARSON, "ORELA MEASUREMENTS TO MEET FUSION ENERGY 2931 1451 76 NEUTRON CROSS SECTION NEEDS," PROC. SYMP. ON CROSS-SECTIONS 2931 1451 77 FROM 10-50 MEV, BNL-NCS-51245, BROOKHAVEN NATIONAL 2931 1451 78 LAB. (JULY,1980). 2931 1451 79 (10) P. GUENTHER ET.AL, ARGONNE NATIONAL LAB DATA IN CSISRS WITH 2931 1451 80 AN/SAN 12869/002, AND W.P. POENITZ AND J.F. WHALEN, ANL/NDM802931 1451 81 IN CSISRS WITH AN/SAN 12853/ , BOTH DATED 1983. 2931 1451 82 (11) A.I. DYUMIN, D.M. KAMINKER, G.N. POPOVA, & V.A. SMOLIN, 2931 1451 83 IZV.AKAD.NAUK SSSR, SER.FIZ. 36 (4), 852 (1972) 2931 1451 84 (12) D.M. HETRICK AND C.Y. FU, "GLUCS: A GENERALIZED LEAST SQUARES2931 1451 85 PROGRAM FOR UPDATING CROSS SECTION EVALUATIONS WITH 2931 1451 86 CORRELATED DATA SETS," ORNL/TM-7341, ENDF-303 (OCT,1980). 2931 1451 87 (13) C.Y. FU AND D.M. HETRICK, "EXPERIENCE IN USING THE 2931 1451 88 COVARIANCES OF SOME ENDF/B-V DOSIMETRY CROSS SECTIONS: 2931 1451 89 PROPOSED IMPROVEMENTS AND ADDITIONS OF CROSS-REACTION 2931 1451 90 COVARIANCES," PROC. FOURTH ASTM-EURATOM SYMP. ON REACTOR 2931 1451 91 DOSIMETRY, GAITHERSBURG, MARYLAND, MARCH 22-26,1982, P877, 2931 1451 92 US NATIONAL BUREAU OF STANDARDS. 2931 1451 93 (14) CSISRS LIBRARY, NATIONAL NUCLEAR DATA CENTER, BROOKHAVEN 2931 1451 94 NATIONAL LABORATORY, UPTON, N.Y. 11973. 2931 1451 95 (15) V. MCLANE, C.L. DUNFORD AND P.F. ROSE, "NEUTRON CROSS 2931 1451 96 SECTIONS, VOL. 2, NEUTRON CROSS SECTION CURVES", ACADEMIC 2931 1451 97 PRESS, 1988. 2931 1451 98 (16) S.M. QAIM AND G. STOCKLIN, NUCL. PHYS. A257 (1976). 2931 1451 99 (17) S.M. QAIM, RADIOCHIMICA ACTA, 25, 13-16 (1978). 2931 1451 100 (18) M. G. DELFINI ET AL., NUCL. PHYS. A404, 250 (1983). 2931 1451 101 ***************** PROGRAM LINEAR (VERSION 89-1) *****************2931 1451 102 DATA LINEARIZED TO WITHIN AN ACCURACY OF 0.100 PER-CENT 2931 1451 103 **************** PROGRAM GROUPIE (VERSION 89-1) *****************2931 1451 104 UNSHIELDED GROUP AVERAGES USING 640 GROUPS (SAND-II EXTEND) 2931 1451 105 FLAT WEIGHTING SPECTRUM 2931 1451 106 2931 1451 107 1 451 110 12931 1451 108 3 16 37 12931 1451 109 33 16 62 12931 1451 110 2931 1 099999 2931 0 0 0 2.90650+ 4 6.43700+ 1 0 0 0 02931 3 16 1 -9.91000+ 6-9.91000+ 6 0 0 1 1012931 3 16 2 101 1 2931 3 16 3 1.00000+ 7 3.89257- 4 1.01000+ 7 4.94746- 3 1.02000+ 7 1.06342- 22931 3 16 4 1.03000+ 7 1.63209- 2 1.04000+ 7 2.20077- 2 1.05000+ 7 3.67329- 22931 3 16 5 1.06000+ 7 6.04967- 2 1.07000+ 7 8.42605- 2 1.08000+ 7 1.08024- 12931 3 16 6 1.09000+ 7 1.31788- 1 1.10000+ 7 1.59085- 1 1.11000+ 7 1.89915- 12931 3 16 7 1.12000+ 7 2.20745- 1 1.13000+ 7 2.51575- 1 1.14000+ 7 2.82405- 12931 3 16 8 1.15000+ 7 3.14504- 1 1.16000+ 7 3.47872- 1 1.17000+ 7 3.81240- 12931 3 16 9 1.18000+ 7 4.14608- 1 1.19000+ 7 4.47976- 1 1.20000+ 7 4.80101- 12931 3 16 10 1.21000+ 7 5.10983- 1 1.22000+ 7 5.41865- 1 1.23000+ 7 5.72747- 12931 3 16 11 1.24000+ 7 6.03629- 1 1.25000+ 7 6.30458- 1 1.26000+ 7 6.53234- 12931 3 16 12 1.27000+ 7 6.76010- 1 1.28000+ 7 6.98786- 1 1.29000+ 7 7.21562- 12931 3 16 13 1.30000+ 7 7.41987- 1 1.31000+ 7 7.60061- 1 1.32000+ 7 7.78135- 12931 3 16 14 1.33000+ 7 7.96209- 1 1.34000+ 7 8.14283- 1 1.35000+ 7 8.30519- 12931 3 16 15 1.36000+ 7 8.44917- 1 1.37000+ 7 8.59315- 1 1.38000+ 7 8.73713- 12931 3 16 16 1.39000+ 7 8.88111- 1 1.40000+ 7 9.00663- 1 1.41000+ 7 9.11369- 12931 3 16 17 1.42000+ 7 9.22075- 1 1.43000+ 7 9.32781- 1 1.44000+ 7 9.43487- 12931 3 16 18 1.45000+ 7 9.52211- 1 1.46000+ 7 9.58953- 1 1.47000+ 7 9.65695- 12931 3 16 19 1.48000+ 7 9.72437- 1 1.49000+ 7 9.79179- 1 1.50000+ 7 9.85605- 12931 3 16 20 1.51000+ 7 9.91715- 1 1.52000+ 7 9.97824- 1 1.53000+ 7 1.00393+ 02931 3 16 21 1.54000+ 7 1.01004+ 0 1.55000+ 7 1.01484+ 0 1.56000+ 7 1.01832+ 02931 3 16 22 1.57000+ 7 1.02180+ 0 1.58000+ 7 1.02528+ 0 1.59000+ 7 1.02876+ 02931 3 16 23 1.60000+ 7 1.03373+ 0 1.61000+ 7 1.04019+ 0 1.62000+ 7 1.04665+ 02931 3 16 24 1.63000+ 7 1.05311+ 0 1.64000+ 7 1.05957+ 0 1.65000+ 7 1.06363+ 02931 3 16 25 1.66000+ 7 1.06529+ 0 1.67000+ 7 1.06695+ 0 1.68000+ 7 1.06861+ 02931 3 16 26 1.69000+ 7 1.07027+ 0 1.70000+ 7 1.07157+ 0 1.71000+ 7 1.07251+ 02931 3 16 27 1.72000+ 7 1.07345+ 0 1.73000+ 7 1.07439+ 0 1.74000+ 7 1.07533+ 02931 3 16 28 1.75000+ 7 1.07734+ 0 1.76000+ 7 1.08042+ 0 1.77000+ 7 1.08350+ 02931 3 16 29 1.78000+ 7 1.08658+ 0 1.79000+ 7 1.08966+ 0 1.80000+ 7 1.08975+ 02931 3 16 30 1.81000+ 7 1.08685+ 0 1.82000+ 7 1.08395+ 0 1.83000+ 7 1.08105+ 02931 3 16 31 1.84000+ 7 1.07815+ 0 1.85000+ 7 1.07277+ 0 1.86000+ 7 1.06491+ 02931 3 16 32 1.87000+ 7 1.05706+ 0 1.88000+ 7 1.04920+ 0 1.89000+ 7 1.04134+ 02931 3 16 33 1.90000+ 7 1.03349+ 0 1.91000+ 7 1.02563+ 0 1.92000+ 7 1.01777+ 02931 3 16 34 1.93000+ 7 1.00992+ 0 1.94000+ 7 1.00206+ 0 1.95000+ 7 9.94204- 12931 3 16 35 1.96000+ 7 9.86347- 1 1.97000+ 7 9.78491- 1 1.98000+ 7 9.70635- 12931 3 16 36 1.99000+ 7 9.62778- 1 2.00000+ 7 0.00000+ 0 2931 3 16 37 2931 3 099999 2931 0 0 0 2.90650+ 4 6.4370E+01 0 0 0 1293133 16 1 0.0000E+00 0.0000E+00 0 16 0 2293133 16 2 0.0000E+00 0.0000E+00 1 5 300 24293133 16 3 1.0000E-05 1.0100E+07 1.0500E+07 1.1000E+07 1.1500E+07 1.2000E+07293133 16 4 1.2500E+07 1.3000E+07 1.3500E+07 1.4000E+07 1.4500E+07 1.5000E+07293133 16 5 1.5500E+07 1.6000E+07 1.6500E+07 1.7000E+07 1.7500E+07 1.8000E+07293133 16 6 1.8500E+07 1.9000E+07 1.9200E+07 1.9400E+07 1.9600E+07 2.0000E+07293133 16 7 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00293133 16 8 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00293133 16 9 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00293133 16 10 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9.2849E-02293133 16 11 -3.9100E-03 9.8124E-04 3.2315E-04 2.5973E-04 1.6943E-04 1.0837E-04293133 16 12 5.2219E-05 4.5076E-05 3.6396E-05 1.4418E-05 2.1146E-05 2.1805E-05293133 16 13 2.1931E-05 2.1318E-05 2.1522E-05 2.2348E-05 2.9580E-05 2.2389E-05293133 16 14 2.5489E-05 2.5389E-05 2.8747E-05 1.1582E-03 9.4407E-05 2.2976E-04293133 16 15 1.6573E-04 1.1914E-04 8.3873E-05 4.3373E-05 3.6631E-05 3.1684E-05293133 16 16 1.1438E-05 1.8007E-05 1.8412E-05 1.8521E-05 1.7912E-05 1.8306E-05293133 16 17 1.8801E-05 2.5446E-05 1.8989E-05 2.1853E-05 2.1701E-05 2.4893E-05293133 16 18 1.0426E-03 4.1291E-04 3.5993E-04 2.4206E-04 1.6476E-04 8.2857E-05293133 16 19 7.0722E-05 6.0039E-05 2.2260E-05 3.4439E-05 3.5246E-05 3.5284E-05293133 16 20 3.4112E-05 3.4653E-05 3.5725E-05 4.7927E-05 3.4885E-05 4.0981E-05293133 16 21 4.0699E-05 4.6995E-05 1.6804E-03 5.1367E-04 3.7077E-04 2.3022E-04293133 16 22 1.0876E-04 9.5181E-05 7.5902E-05 3.0612E-05 4.4708E-05 4.6020E-05293133 16 23 4.5981E-05 4.4753E-05 4.5221E-05 4.6593E-05 6.1095E-05 4.5008E-05293133 16 24 5.2412E-05 5.2045E-05 5.9698E-05 1.5662E-03 4.6015E-04 3.0034E-04293133 16 25 1.3181E-04 1.1846E-04 8.7882E-05 3.8955E-05 5.3423E-05 5.5298E-05293133 16 26 5.5174E-05 5.4093E-05 5.4391E-05 5.6078E-05 7.1784E-05 5.4017E-05293133 16 27 6.1977E-05 6.1527E-05 6.9508E-05 1.6388E-03 3.8739E-04 1.8183E-04293133 16 28 1.6833E-04 1.0963E-04 5.4807E-05 6.8444E-05 7.1184E-05 7.0989E-05293133 16 29 6.9696E-05 7.0329E-05 7.2399E-05 9.1321E-05 7.1362E-05 7.9338E-05293133 16 30 7.8939E-05 8.7688E-05 1.6381E-03 2.7820E-04 2.9569E-04 1.5183E-04293133 16 31 8.4051E-05 9.2687E-05 9.9014E-05 9.7400E-05 9.5524E-05 9.6112E-05293133 16 32 9.8898E-05 1.2500E-04 9.5565E-05 1.0835E-04 1.0739E-04 1.2076E-04293133 16 33 7.2642E-04 1.3861E-04 2.1090E-04 1.3154E-04 1.2590E-04 1.3899E-04293133 16 34 1.3473E-04 1.3248E-04 1.3243E-04 1.3654E-04 1.7246E-04 1.2855E-04293133 16 35 1.4860E-04 1.4753E-04 1.6696E-04 7.4020E-04 2.2844E-04 1.3272E-04293133 16 36 1.3480E-04 1.4740E-04 1.4311E-04 1.4019E-04 1.4023E-04 1.4475E-04293133 16 37 1.8498E-04 1.3536E-04 1.5870E-04 1.5766E-04 1.7994E-04 2.5205E-04293133 16 38 6.7831E-05 1.5774E-04 1.5403E-04 1.5480E-04 1.4692E-04 1.4845E-04293133 16 39 1.5385E-04 2.1458E-04 1.4114E-04 1.7986E-04 1.7866E-04 2.1467E-04293133 16 40 4.9848E-04 7.7213E-05 1.8584E-04 1.5113E-04 1.7339E-04 1.6481E-04293133 16 41 1.6703E-04 1.1799E-04 1.6769E-04 1.2330E-04 1.2252E-04 8.4028E-05293133 16 42 3.4942E-04 1.7432E-04 1.9975E-04 2.0482E-04 1.8271E-04 1.7572E-04293133 16 43 1.6743E-04 1.7022E-04 1.5696E-04 1.5582E-04 1.4329E-04 5.2876E-04293133 16 44 1.9487E-04 2.1525E-04 1.9401E-04 1.9702E-04 1.6642E-04 1.6184E-04293133 16 45 1.5555E-04 1.5458E-04 1.4089E-04 2.9887E-04 1.8750E-04 2.0981E-04293133 16 46 1.8656E-04 1.7332E-04 1.7942E-04 1.6365E-04 1.6255E-04 1.4448E-04293133 16 47 3.3467E-04 2.2613E-04 2.0243E-04 1.7545E-04 1.8875E-04 1.6806E-04293133 16 48 1.6691E-04 1.4225E-04 1.1229E-03-7.4862E-05 3.1309E-04 2.2013E-04293133 16 49 2.7176E-04 2.6985E-04 1.8472E-04 4.9986E-04 1.6697E-04 2.0915E-04293133 16 50 1.7615E-04 1.7495E-04 1.4909E-04 1.3873E-03 1.1714E-04 5.8852E-04293133 16 51 5.8437E-04 3.4575E-04 4.7121E-04 2.5339E-04 2.5176E-04 1.7365E-04293133 16 52 3.0426E-03 1.1867E-03 9.8857E-04 3.0015E-03 9.8197E-04 2.7731E-03293133 16 53 0.0000E+00 0.0000E+00 0 8 48 24293133 16 54 1.0000E-05 0.0000E+00 1.0100E+07 1.8167E-06 1.0500E+07 9.2309E-07293133 16 55 1.1000E+07 5.7456E-06 1.1500E+07 2.8213E-05 1.2000E+07 5.2413E-05293133 16 56 1.2500E+07 8.4423E-05 1.3000E+07 1.1260E-04 1.3500E+07 6.0382E-05293133 16 57 1.4000E+07 7.0182E-05 1.4500E+07 2.6190E-05 1.5000E+07 5.5253E-05293133 16 58 1.5500E+07 4.0563E-05 1.6000E+07 6.4379E-05 1.6500E+07 3.7846E-05293133 16 59 1.7000E+07 4.2917E-05 1.7500E+07 1.4672E-04 1.8000E+07 6.5269E-05293133 16 60 1.8500E+07 1.7207E-04 1.9000E+07 5.8043E-05 1.9200E+07 3.7985E-04293133 16 61 1.9400E+07 3.6370E-04 1.9600E+07 3.0778E-04 2.0000E+07 2.6557E-04293133 16 62 293133 099999 2931 0 0 0 0 0 0 0 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0