29-Cu- 63 ENDF/B-VI, Processed by Red Cullen using PREPRO2004 6000 0 0 0 2.90630E+4 6.23890E+1 2 0 0 52925 1451 1 0.0 0.0 0 0 0 62925 1451 2 1.00000E+0 1.50000E+8 8 0 10 62925 1451 3 0.0 0.0 1 0 500 1502925 1451 4 29-Cu- 63 LANL,ORNL EVAL-FEB98 A.KONING,M.CHADWICK,HETRICK 2925 1451 5 Ch98,Ch99 DIST-SEP 1 REV4- 20010926 2925 1451 6 ----ENDF/B-VI MATERIAL 2925 REVISION 3 2925 1451 7 -----INCIDENT NEUTRON DATA 2925 1451 8 ------ENDF-6 FORMAT 2925 1451 9 2925 1451 10 **************************************************************** 2925 1451 11 2925 1451 12 ENDF/B-VI MOD 5 Revision, May 2000, S.C. Frankle, R.C. Reedy, 2925 1451 13 P.G. Young (LANL) 2925 1451 14 2925 1451 15 The secondary gamma-ray spectrum for radiative capture (MF 12, 2925 1451 16 MT 102) has been updated for new experimental data at incident 2925 1451 17 neutron energies up to 1 keV. The Q-value for radiative capture 2925 1451 18 was also updated in File 3. 2925 1451 19 Details of these changes are described in Frankel et al. [Fr01]. 2925 1451 20 2925 1451 21 **************************************************************** 2925 1451 22 2925 1451 23 ENDF/B-VI MOD 4 Evaluation, February 1998, A.J. Koning (ECN), 2925 1451 24 M.B. Chadwick, P.G. Young (LANL) 2925 1451 25 2925 1451 26 Los Alamos LA150 Library, produced with FKK/GNASH/GSCAN code 2925 1451 27 in cooperation with ECN Petten. 2925 1451 28 2925 1451 29 This evaluation provides a complete representation of the 2925 1451 30 nuclear data needed for transport, damage, heating, 2925 1451 31 radioactivity, and shielding applications over the incident 2925 1451 32 neutron energy range from 1.0E-11 to 150 MeV. The discussion 2925 1451 33 here is divided into the region below and above 20 MeV. 2925 1451 34 2925 1451 35 INCIDENT NEUTRON ENERGIES < 20 MeV 2925 1451 36 2925 1451 37 Below 20 MeV the evaluation is based completely on the ENDF/B- 2925 1451 38 VI (Mod 3) evaluation by D. Hetrick, C.Y. Fu, and D. Larson. 2925 1451 39 2925 1451 40 INCIDENT NEUTRON ENERGIES > 20 MeV 2925 1451 41 2925 1451 42 The ENDF/B-VI Release 2 evaluation extends to 20 MeV and 2925 1451 43 includes cross sections and energy-angle data for all 2925 1451 44 significant reactions. The present evaluation utilizes a more 2925 1451 45 compact composite reaction spectrum representation above 20 MeV 2925 1451 46 in order to reduce the length of the file. No essential data for 2925 1451 47 applications is lost with this representation. 2925 1451 48 The evaluation above 20 MeV utilizes MF=6, MT=5 to represent 2925 1451 49 all reaction data. Production cross sections and emission 2925 1451 50 spectra are given for neutrons, protons, deuterons, tritons, 2925 1451 51 alpha particles, gamma rays, and all residual nuclides produced 2925 1451 52 (A>5) in the reaction chains. To summarize, the ENDF sections 2925 1451 53 with non-zero data above En = 20 MeV are: 2925 1451 54 2925 1451 55 MF=3 MT= 1 Total Cross Section 2925 1451 56 MT= 2 Elastic Scattering Cross Section 2925 1451 57 MT= 3 Nonelastic Cross Section 2925 1451 58 MT= 5 Sum of Binary (n,n') and (n,x) Reactions 2925 1451 59 2925 1451 60 MF=4 MT= 2 Elastic Angular Distributions 2925 1451 61 2925 1451 62 MF=6 MT= 5 Production Cross Sections and Energy-Angle 2925 1451 63 Distributions for Emission Neutrons, Protons, 2925 1451 64 Deuterons, Tritons, and Alphas; and Angle- 2925 1451 65 Integrated Spectra for Gamma Rays and Residual 2925 1451 66 Nuclei That Are Stable Against Particle Emission 2925 1451 67 2925 1451 68 The evaluation is based on nuclear model calculations that 2925 1451 69 have been benchmarked to experimental data, especially for n + 2925 1451 70 Cu65 and p + Cu65 reactions [Ch98]. We use the GNASH code system 2925 1451 71 [Yo92], which utilizes Hauser-Feshbach statistical, preequilib- 2925 1451 72 rium and direct-reaction theories. Spherical optical model 2925 1451 73 calculations are used to obtain particle transmission 2925 1451 74 coefficients for the Hauser-Feshbach calculations, as well as 2925 1451 75 for the elastic neutron angular distributions. 2925 1451 76 Cross sections and spectra for producing individual residual 2925 1451 77 nuclei are included for reactions. The energy-angle-correlations 2925 1451 78 for all outgoing particles are based on Kalbach systematics 2925 1451 79 [Ka88]. 2925 1451 80 A model was developed to calculate the energy distributions of 2925 1451 81 all recoil nuclei in the GNASH calculations [Ch96a]. The recoil 2925 1451 82 energy distributions are represented in the laboratory system in 2925 1451 83 MT=5, MF=6, and are given as isotropic in the lab system. All 2925 1451 84 other data in MT=5,MF=6 are given in the center-of-mass system. 2925 1451 85 This method of representation utilizes the LCT=3 option approved 2925 1451 86 at the November, 1996, CSEWG meeting. 2925 1451 87 Preequilibrium corrections were performed in the course of the 2925 1451 88 GNASH calculations using the exciton model of Kalbach [Ka77, 2925 1451 89 Ka85], validated by comparison with calculations using Feshbach, 2925 1451 90 Kerman, Koonin (FKK) theory [Ch93]. Discrete level data from 2925 1451 91 nuclear data sheets were matched to continuum level densities 2925 1451 92 using the formulation of Ignatyuk et al. [Ig75] and pairing and 2925 1451 93 shell parameters from the Cook [Co67] analysis. Neutron and 2925 1451 94 charged- particle transmission coefficients were obtained from 2925 1451 95 the optical potentials, as discussed below. Gamma-ray 2925 1451 96 transmission coefficients were calculated using the Kopecky-Uhl 2925 1451 97 model [Ko90]. 2925 1451 98 2925 1451 99 SPECIFIC INFORMATION CONCERNING THE 63Cu EVALUATION 2925 1451 100 2925 1451 101 This evaluation is documented in some detail in Ref. [Ko98b]. 2925 1451 102 2925 1451 103 The neutron total cross section above 20 MeV was obtained by 2925 1451 104 evaluating experimental data, with a particular emphasis on the 2925 1451 105 Finlay [Fi93] elemental data. This resulted in an evaluated 2925 1451 106 elemental Cu total cross section; to obtain an isotopic 63Cu total2925 1451 107 cross section, it was assumed that 63Cu and 65Cu have total cross 2925 1451 108 sections in an A**2/3 ratio to one another. The total neutron 2925 1451 109 nonelastic cross section was obtained directly from an optical 2925 1451 110 model calculation (see below), after verifying that it was in good2925 1451 111 agreement with the experimental data [Ko98b]. 2925 1451 112 2925 1451 113 To obtain the neutron optical potential we used total cross 2925 1451 114 section data from 1.2 to 4.5 MeV [Gu86] and from 5.3 to 600 MeV 2925 1451 115 [Fi93], and elastic scattering angular distribution data from 1.6 2925 1451 116 to 96 MeV [Br50, Sa60, Ki74, El82, Gu86]. The optical potential 2925 1451 117 parameters were obtained using a combination of a grid search code2925 1451 118 and the interactive optical model viewer ECISVIEW [Ko97], both 2925 1451 119 built around the coupled channels code ECIS96 [Ra94]. The energy 2925 1451 120 dependence of the optical model parameters is as described in 2925 1451 121 [Ko98]. This optical potential was used for the calculation, with 2925 1451 122 ECIS96, of neutron transmission coefficients and DWBA cross 2925 1451 123 sections for the entire energy region above 20 MeV. 2925 1451 124 2925 1451 125 Due to the lack of proton elastic scattering data in numerical 2925 1451 126 form, we used a combination of global optical models for the 2925 1451 127 proton channel. The Becchetti-Greenlees potential [Be69]was 2925 1451 128 adopted below 47 MeV, and the non-relativistic version of the 2925 1451 129 Madland potential [Ma88] above 47 MeV. At this particular energy 2925 1451 130 point the two potentials join smoothly. 2925 1451 131 2925 1451 132 For deuterons, the Lohr-Haeberli global potential [Lo74] was used;2925 1451 133 for alpha particles the Moyen potential (MacFadden-Satchler 2925 1451 134 [Ma66]) was used; and for tritons the Becchetti-Greenlees 2925 1451 135 potential [Be71] was used. The He-3 channel was ignored, due to 2925 1451 136 its small importance. 2925 1451 137 2925 1451 138 Following Delaroche et al. [De82], we adopted the weak-coupling 2925 1451 139 model for direct collective inelastic scattering for Cu-63, using 2925 1451 140 Ni-64 as a basis. For the calculation of the cross sections, 2925 1451 141 ECIS96 was used in DWBA mode. We used the following direct 2925 1451 142 transitions for Cu-63 (ground state 3/2- ) : 2925 1451 143 2925 1451 144 Jpi Ex(MeV) Deformation lengths 2925 1451 145 0.5- 0.669 Delta(2)=0.319 2925 1451 146 2.5- 0.962 Delta(2)=0.552 2925 1451 147 3.5- 1.327 Delta(2)=0.638 2925 1451 148 1.5- 1.547 Delta(2)=0.451 2925 1451 149 1.5- 3.382 Delta(3)=0.313 2925 1451 150 2.5- 3.632 Delta(3)=0.384 2925 1451 151 3.5- 3.882 Delta(3)=0.444 2925 1451 152 4.5- 4.132 Delta(3)=0.496 2925 1451 153 2925 1451 154 No measurements exist for neutron-induced emission spectra above 2925 1451 155 20 MeV for 63Cu. However, for Cu-65 there exists 25.7 MeV (n,xn) 2925 1451 156 data by Marcinkowski et al [Ma83]. This has been used to benchmark2925 1451 157 the Cu-65 data. Without adjusting any of the level density or pre-2925 1451 158 equilibrium parameters the GNASH calculation was in good agreement2925 1451 159 with these data. Hence we also adopted these parameters for the 2925 1451 160 whole energy region for Cu-63. 2925 1451 161 2925 1451 162 **************************************************************** 2925 1451 163 2925 1451 164 REFERENCES 2925 1451 165 2925 1451 166 [Ab93] W. Abfalterer, R.W. Finlay, S.M. Grimes, and V. Mishra, 2925 1451 167 Phys.Rev. C47, 1033 (1993) 2925 1451 168 [Al83] R. Alarcon and J. Rapaport, Nucl.Phys. A458, 502 (1986) 2925 1451 169 [Ar80] E.D. Arthur and P.G. Young, 'Evaluation of Neutron Cross 2925 1451 170 Sections to 40 MeV for 54,56Fe," Proc. Sym. on Neutron Cross 2925 1451 171 Sections from 10 to 50 MeV, 12-14 May 1980, Brookhaven National2925 1451 172 Laboratory [Eds. M. R. Bhat and S. Pearlstein, BNL-NCS- 51245, 2925 1451 173 1980] p. 731. 2925 1451 174 [Be69] F.D. Becchetti, Jr., and G.W. Greenlees, Phys.Rev. 182, 2925 1451 175 1190 (1969) 2925 1451 176 [Be71] F.D. Becchetti, Jr., and G.W. Greenlees in "Polarization 2925 1451 177 Phenomena in Nuclear Reactions," (Ed: H.H. Barschall and W. 2925 1451 178 Haeberli, The University of Wisconsin Press, 1971) p.682. 2925 1451 179 [Be92] O. Bersillon, "SCAT2 - A Spherical Optical Model Code," 2925 1451 180 in Proc. ICTP Workshop on Computation and Analysis of Nuclear 2925 1451 181 data Relevant to Nuclear Energy and Safety, February-March, 2925 1451 182 1999 Trieste, Italy, to be published in World Scientific Press,2925 1451 183 and Progress Report of the Nuclear Physics Division, Bruyeres- 2925 1451 184 le-Chatel 1977, CEA-N-2037 (1978) p.111 2925 1451 185 [Br50] S. Bratenahl, S. Fernbach, R.H. Hildebrand et al., 2925 1451 186 Phys.Rev. 77, 597 (1950) 2925 1451 187 [Ch93] M.B. Chadwick and P.G. Young, Phys.Rev. C 47, 2255 (1993) 2925 1451 188 [Ch96] M.B. Chadwick, P.G. Young, R.E. MacFarlane, and A.J. 2925 1451 189 Koning, "High-Energy Nuclear Data Libraries for Accelerator- 2925 1451 190 Driven Technologies: Calculational Method for Heavy Recoils," 2925 1451 191 Proc. of 2nd Int. Conf. on Accelerator Driven Transmutation 2925 1451 192 Technology and Applications, Kalmar, Sweden, 3-7 June 1996 2925 1451 193 [Ch98] M. B. Chadwick and P. G. Young, "GNASH Calculations of 2925 1451 194 n,p + Cu isotopes and Benchmarking of Results" in APT PROGRESS 2925 1451 195 REPORT: 1 February - 1 March 1998, internal Los Alamos National2925 1451 196 Laboratory memo, 6 Mar.1998 from R.E. MacFarlane to L. Waters. 2925 1451 197 [Ch99] M.B. Chadwick, P G. Young, G. M. Hale, et al., Los Alamos 2925 1451 198 National Laboratory report, LA-UR-99-1222 (1999) 2925 1451 199 [Co67] J.L. Cook, H. Ferguson, and A.R. DeL Musgrove, Aust.J. 2925 1451 200 Phys. 20, 477 (1967) 2925 1451 201 [De82] J.P. Delaroche, S.M. El-Kadi, P.P. Guss, C.E. Floyd and 2925 1451 202 R.L. Walter, Nucl. Phys. A390, 541 (1982). 2925 1451 203 [El82] S.M. El-Kadi, C.E. Nelson, F.O. Purser et al., Nucl.Phys. 2925 1451 204 A390, 509 (1982) 2925 1451 205 [Fi93] R. W. Finlay, W. P. Abfalterer, G. Fink et al., Phys.Rev. 2925 1451 206 C 47, 237 (1993) 2925 1451 207 [Fr01] S.C. Frankle, R.C. Reedy, and P.G. Young, Los ALamos 2925 1451 208 National Laboratory Report, LA-13812 (2001). 2925 1451 209 [Gu86] P. Guenther, D.L. Smith, A.B. Smith, J.F. Whalen, Nucl. 2925 1451 210 Phys. A448, 280 (1986) 2925 1451 211 [Ig75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov.J. 2925 1451 212 Nucl.Phys. 21, 255 (1975); translation of Yad.Fiz. 21, 485 2925 1451 213 (1975) 2925 1451 214 [Ka77] C. Kalbach, Z.Phys.A 283, 401 (1977) 2925 1451 215 [Ka85] C. Kalbach, Los Alamos National Laboratory report 2925 1451 216 LA-10248-MS (1985) 2925 1451 217 [Ka88] C. Kalbach, Phys.Rev.C 37, 2350 (1988); see also 2925 1451 218 C. Kalbach and F. M. Mann, Phys.Rev.C 23, 112 (1981) 2925 1451 219 [Ki74] W.E. Kinney, F.G. Perey, Oak Ridge report ORNL-4908 (1974)2925 1451 220 [Ko90] J. Kopecky and M. Uhl, Phys.Rev.C 41, 1941 (1990) 2925 1451 221 [Ko97] A.J. Koning, J.J. van Wijk and J.-P. Delaroche, "ECISVIEW:2925 1451 222 A Graphical Interface for ECIS95", Proceedings of the NEA 2925 1451 223 Specialists' Meeting on the Nucleon Nucleus Optical Model up to2925 1451 224 200 MeV, Bruyeres-le-Chatel, November 13-15 1996. Available at 2925 1451 225 http://db.nea.fr/html/science/om200/. 2925 1451 226 [Ko98] A.J. Koning, J.-P. Delaroche and O. Bersillon, "Nuclear 2925 1451 227 Data for Accelerator-Driven Systems: Nuclear models, Experiment2925 1451 228 and Data Libraries", to appear in Mucl. Instr. Meth. A (1998). 2925 1451 229 [Ko98b] A.J. Koning, M.B. Chadwick, and P.G. Young, "ENDF/B-VI 2925 1451 230 neutron and proton datafiles up to 150 MeV for 63Cu and 65Cu", 2925 1451 231 Los Alamos National Laboratory report LAUR- (1998); ECN lab and2925 1451 232 JEFF report (1998). 2925 1451 233 [Lo74] J.M. Lohr and W. Haeberli, Nucl.Phys. A232, 381 (1974) 2925 1451 234 [Ma66] Macfadden and Satchler, Nuc.Phys. 84, 177 (1966) 2925 1451 235 [Ma83] A. Marcinkowski, R.W. Finlay, G. Randers-Pehrson et al., 2925 1451 236 Nucl.Phys. A402, 220 (1983) 2925 1451 237 [Ma88] D.G. Madland, "Recent Results in the Development of a 2925 1451 238 Global Medium-Energy Nucleon-Nucleus Optical-Model Potential, 2925 1451 239 "Proc. OECD/NEANDC Specialist's Mtg. on Preequilibrium Nuclear 2925 1451 240 Reactions, Semmering, Austria, 10-12 Feb. 1988, NEANDC-245 'U' 2925 1451 241 (1988). 2925 1451 242 [Pe63] C.M. Perey and F.G. Perey, Phys.Rev. 132, 755 (1963) 2925 1451 243 [Ra94] J. Raynal, Notes on ECIS94, CEA Saclay Report CEA-N-2772 2925 1451 244 (1994) 2925 1451 245 [Sa60] G.L. Salmon, Nucl.Phys. 21, 15 (1960) 2925 1451 246 [Yo92] P.G. Young, E.D. Arthur, and M.B. Chadwick, report 2925 1451 247 LA-12343-MS (1992) 2925 1451 248 2925 1451 249 **************************************************************** 2925 1451 250 2925 1451 251 ENDF/B-VI MOD 3 Revision, July 1991 (ORNL) 2925 1451 252 2925 1451 253 MOD 3 changes 2925 1451 254 1) Corrections to MF=6, MT=65 at 17.0 MeV to prevent negative 2925 1451 255 values in the angular distribution. 2925 1451 256 2) Corrections to MF=33, MT=102 2925 1451 257 2925 1451 258 **************************************************************** 2925 1451 259 2925 1451 260 * Note there was no MOD 2 released. 2925 1451 261 2925 1451 262 **************************************************************** 2925 1451 263 2925 1451 264 ENDF/B-VI MOD 1 Evaluation, October 1989, D. Hetrick, F.Y. Fu, 2925 1451 265 D. Larson (ORNL) 2925 1451 266 2925 1451 267 This work employed several nuclear model codes including the 2925 1451 268 optical-model code GENOA [1], the Distorted Wave Born 2925 1451 269 Approximation (DWBA) program DWUCK [2], and the Hauser-Feshbach 2925 1451 270 code TNG [3,4]. The TNG code provides energy and angular 2925 1451 271 distributions of particles emitted in the compound and pre- 2925 1451 272 compound reactions, ensures consistency among all reactions, and 2925 1451 273 maintains energy balance. Details pertinent to the contents of 2925 1451 274 this evaluation and extensive comparisons of calculations with 2925 1451 275 experimental data can be found in reference [5]. 2925 1451 276 2925 1451 277 ----- DESCRIPTION OF FILES 2925 1451 278 (MF-MT) 2925 1451 279 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2925 1451 280 2-151 RESONANCE PARAMETERS WERE TAKEN FROM MUGHABGHAB[6]. POINT2925 1451 281 WISE RECONSTRUCTION COMPARED WITH DATA [7] SHOWED POORER 2925 1451 282 FIT ABOVE 100 KEV, SO THE RESONANCE REGION WAS CUT OFF AT 2925 1451 283 99.5 KEV. REICH-MOORE PARAMETERS ARE GIVEN. AGREEMENT 2925 1451 284 WITH DATA COULD BE IMPROVED WITH ADDITION OF A BACKGROUND 2925 1451 285 FILE IN 3/1, BUT THIS IN GENERAL GIVES TOO LARGE AN 2925 1451 286 AVERAGE CROSS SECTION, WHEN BINNED IN 10 KEV BINS AND 2925 1451 287 COMPARED WITH THE BINNED DATA. THIS IS PROBABLY DUE TO 2925 1451 288 TOO LARGE AN ESTIMATE OF NEUTRON WIDTHS FOR RESONANCES 2925 1451 289 SEEN ONLY IN CAPTURE AND NOT IN TRANSMISSION. 2925 1451 290 NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2925 1451 291 OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE 2925 1451 292 PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON 2925 1451 293 A FINER ENERGY GRID THAN GIVEN IN 4/2. 2925 1451 294 3-1 THE TOTAL CROSS SECTION IS GIVEN BY RESONANCE PARAMETERS 2925 1451 295 FROM 1.E-5 EV TO 99.5 KEV. FROM 1.E-5 TO 1 EV, -0.9B IS 2925 1451 296 GIVEN TO REDUCE THE ELASTIC AND GIVE THE CORRECT TOTAL 2925 1451 297 THERMAL CROSS SECTION (9.6 B). FROM 1 EV TO 170 EV THIS 2925 1451 298 GOES LINEARLY TO ZERO. A SMALL CONTRIBUTION FROM 3/102 IS2925 1451 299 REQUIRED FROM 60 TO 99.5 KEV, WHICH WHEN ADDED TO 2/151 2925 1451 300 REPRODUCES THE CAPTURE DATA. FROM 99.5 KEV TO 1.12 MEV 2925 1451 301 CU63 DATA FROM [7] IS USED, AFTER APPROPRIATE AVERAGING. 2925 1451 302 ABOVE THIS, NO ISOTOPIC DATA IS AVAILABLE. FROM 1.12 TO 2925 1451 303 4.0 MEV,NAT CU DATA OF PEREY [8] USED IN V5 IS RETAINED. 2925 1451 304 FROM 4.0 TO 20 MEV, NAT CU DATA OF LARSON ET.AL [9] IS 2925 1451 305 AVERAGED AND USED. COMPARISONS FROM 1.2 TO 4.5 2925 1451 306 MEV WITH AVERAGED ARGONNE DATA FOR NAT CU [10] SHOW 2925 1451 307 1% AGREEMENT. 2925 1451 308 3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY 2925 1451 309 SUBTRACTING THE NONELASTIC (3-3) FROM THE TOTAL. THE 2925 1451 310 THERMAL VALUE OF 5.1 B IS REPRODUCED. 2925 1451 311 3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22, 2925 1451 312 3-28, 3-102, 3-103, 3-104, 3-106, AND 3-107. 2925 1451 313 3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, .. 2925 1451 314 .., 3-72, AND 3-91 2925 1451 315 3-16 (N,2N) CROSS SECTIONS WERE TAKEN FROM THE GLUCS [11] 2925 1451 316 CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL- 2925 1451 317 TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS 2925 1451 318 SECTIONS [12]. 2925 1451 319 3-22 (N,NA) CROSS SECTIONS WERE CALCULATED BY THE TNG 2925 1451 320 CODE [3,4,5]. NO DATA AVAILABLE OTHER THAN A-EMISSION. 2925 1451 321 3-28 (N,NP) CROSS SECTIONS WERE CALCULATED BY THE TNG 2925 1451 322 CODE [3,4,5]. DATA SCARCE FOR THIS REACTION (SEE (5)). 2925 1451 323 3-51 TO 3-72 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE 2925 1451 324 FROM TNG [3,4,5] WHICH INCLUDES DIRECT INTERACTION 2925 1451 325 CROSS SECTIONS FROM DWUCK [2] CALCULATIONS. EXTENSIVE 2925 1451 326 COMPARISONS WITH EXPERIMENTAL DATA USED IN THE EVALUATION 2925 1451 327 PROCESS ARE SHOWN IN [5] 2925 1451 328 3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM (TNG 2925 1451 329 CALCULATED). GUIDANCE FROM (N,XN) EMISSION DATA [5]. 2925 1451 330 3-102 (N,G) DATA TAKEN FROM RESONANCE PARAMETERS FROM 1.E-5 EVTO2925 1451 331 99.5 KEV. A SMALL BACKGROUND IS GIVEN HERE WHICH WHEN 2925 1451 332 ADDED TO THE RESONACE CONTRIBUTION REPRODUCES EXPERIMENTAL2925 1451 333 DATA,INCLUDING THE THERMAL VALUE OF 4.50B. V5 DATA FROM 2925 1451 334 99.5 KEV TO 20.0 MEV WERE REPLACED BY POINTS ON A CURVE 2925 1451 335 DRAWN THROUGH DATA FROM THE CSISRS LIBRARY [5,13]; RESULTS2925 1451 336 COMPARABLE TO EYE GUIDE IN REF [14]. 2925 1451 337 3-103 (N,P) CROSS SECTIONS WERE CALCULATED BY THE TNG 2925 1451 338 CODE [3,4,5]. 2925 1451 339 3-104 (N,D) CROSS SECTION - SHAPE OF (N,P) CROSS SECTION USED 2925 1451 340 NORMALIZED TO AVAILABLE DATA [5]. 2925 1451 341 3-106 (N,3HE) CROSS SECTION - SHAPE OF (N,A) CROSS SECTION 2925 1451 342 USED NORMALIZED TO AVAILABLE DATA [15]. 2925 1451 343 3-107 (N,A) CROSS SECTIONS WERE TAKEN FROM THE GLUCS [11] 2925 1451 344 CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL- 2925 1451 345 TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS 2925 1451 346 SECTIONS [12]. 2925 1451 347 4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR 2925 1451 348 ELASTIC SCATTERING ARE RESULTS OF FITTING DATA WITH GENOA.2925 1451 349 IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY 2925 1451 350 THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE 2925 1451 351 PARAMETERS IN 2/151. 2925 1451 352 6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2925 1451 353 NEUTRON AND 62CU RESIDUAL, AND ENERGY DEPENDENT YIELD 2925 1451 354 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2925 1451 355 RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR 2925 1451 356 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2925 1451 357 THE OUTGOING NEUTRON). (N,XN) AND (N,XG) D-D EMISSION 2925 1451 358 DATA HEAVILY USED TO BENCHMARK THE TNG CALCULATIONS [5]. 2925 1451 359 6-22 (N,NA) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2925 1451 360 NEUTRON, ALPHA, AND 59CO RESIDUAL, AND ENERGY DEPENDENT 2925 1451 361 YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE 2925 1451 362 GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2925 1451 363 FOR EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY 2925 1451 364 FOR THE OUTGOING NEUTRON). (N,XA) AND (N,XG) D-D EMISSION2925 1451 365 DATA HEAVILY USED TO BENCHMARK THE TNG CALCULATIONS [5]. 2925 1451 366 6-28 (N,NP) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2925 1451 367 NEUTRON AND 62NI RESIDUAL, AND ENERGY DEPENDENT YIELD 2925 1451 368 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2925 1451 369 RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR 2925 1451 370 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2925 1451 371 THE OUTGOING NEUTRON). (N,XP) AND (N,XG) D-D EMISSION 2925 1451 372 DATA HEAVILY USED TO BENCHMARK THE TNG CALCULATIONS [5]. 2925 1451 373 6-51 THROUGH 6-72 INELASTIC SCATTERING EXCITING LEVELS; EACH 2925 1451 374 SECTION INCLUDES SIMPLE CONSTANT YIELDS FOR THE NEUTRON 2925 1451 375 AND 63CU RESIDUAL; ANGULAR DISTRIBUTIONS ARE GIVEN FOR 2925 1451 376 THE OUTGOING NEUTRON (LEGENDRE COEFFICIENTS COMPUTED 2925 1451 377 BY DWUCK [2] AND TNG [3,4,5]). EXTENSIVE COMPARISONS 2925 1451 378 WITH ANGULAR DISTRIBUTION DATA ARE GIVEN IN REF. [5] 2925 1451 379 6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES 2925 1451 380 SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 63CU 2925 1451 381 RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG 2925 1451 382 CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; CALCULATED2925 1451 383 NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH (ANGULAR 2925 1451 384 DISTRIBUTIONS ARE GIVEN ONLY FOR THE OUTGOING NEUTRON). 2925 1451 385 (N,XN) AND (N,XG) D-D EMISSION DATA HEAVILY USED TO BENCH-2925 1451 386 MARK THE TNG CALCULATIONS [5]. 2925 1451 387 6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P 2925 1451 388 AND 63NI RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2925 1451 389 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2925 1451 390 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2925 1451 391 PRODUCT. (N,XP) AND (N,XG) D-D EMISSION DATA USED TO 2925 1451 392 BENCHMARK THE TNG CALCULATIONS [5]. 2925 1451 393 6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A 2925 1451 394 AND 60CO RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2925 1451 395 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2925 1451 396 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2925 1451 397 PRODUCT. (N,XA) AND (N,XG) D-D EMISSION DATA USED TO 2925 1451 398 BENCHMARK THE TNG CALCULATIONS [5]. 2925 1451 399 12-51 THROUGH 12-72 BRANCHING RATIOS FOR THE LEVELS, COMPILED 2925 1451 400 BY HETRICK ET AL. [5] ARE GIVEN. 2925 1451 401 12-102 (N,G) CAPTURE; THERMAL VALUES TAKEN FROM DELFINI ET AL. 2925 1451 402 [16]. HIGHER-ENERGY VALUES BASED ON TNG CALCULATIONS 2925 1451 403 USING PRIMARY BRANCHING RATIOS OF DELFINI ET AL. FOR 2925 1451 404 S-WAVES 2925 1451 405 14-51 THROUGH 14-72 GAMMA-RAY ANGULAR DISTRIBUTIONS ASSUMED TO 2925 1451 406 BE ISOTROPIC. 2925 1451 407 14-102 (N,G) CAPTURE; ISOTROPIC DISTRIBUTIONS ASSUMED 2925 1451 408 15-102 (N,G) CAPTURE; AS IN 12-102 2925 1451 409 ---------------------------------------------------------------- 2925 1451 410 UNCERTAINTY FILES 2925 1451 411 ALL NON-DERIVED FILES CONTAIN AN LB=8 COMPONENT, AS 2925 1451 412 REQUIRED BY ENDF/B-VI FORMATS 2925 1451 413 2925 1451 414 33-1 TOTAL UNCERTAINTIES GIVEN AS DERIVED FROM 1E-5 TO 200 EV 2925 1451 415 EXPLICIT FROM 200 EV TO 20 MEV, USING LB=0,1 AND 8. 2925 1451 416 33-2 EXPLICIT FROM 1E-5 T0 200 EV, DERIVED FROM 200EV TO 20 MEV2925 1451 417 33-3 DERIVED FROM 1.E-5 TO 99.5 KEV, EXPLICIT USING LB=1,8 FROM2925 1451 418 99.5 KEV TO 20 MEV. 2925 1451 419 33-4 DERIVED FROM THRESHOLD TO 20 MEV. 2925 1451 420 33-16 (N,2N) COVARIANCES WERE TAKEN FROM THE GLUCS [11] 2925 1451 421 CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL- 2925 1451 422 TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS 2925 1451 423 SECTIONS [12]. 2925 1451 424 33-22 (N,NA) UNCERTAINTIES ESTIMATED FROM TNG CALCULATION. 2925 1451 425 33-28 (N,NP) COVARIANCES ESTIMATED FROM TNG CALCULATION. 2925 1451 426 33-51-91 INELASTIC SCATTERING UNCERTAINTIES ESTIMATED FROM DATA 2925 1451 427 AND CALCULATIONS. 2925 1451 428 33-102 CAPTURE UNCERTAINTIES ESTIMATED FROM THERMAL VALUE AT LOW 2925 1451 429 ENERGIES, BINNED DATA IN THE RESONANCE REGION, AND CSISRS 2925 1451 430 DATA [5,13,14] FROM 99.5 KEV TO 20 MEV. 2925 1451 431 33-103 (N,P) COVARIANCES - ESTIMATED AS NO DATA AVAILABLE. 2925 1451 432 33-104 (N,D) COVARIANCES - ESTIMATED, BASED ON DATA. 2925 1451 433 33-106 (N,3HE) COVARIANCES - ESTIMATED, BASED ON DATA. 2925 1451 434 33-107 (N,A) COVARIANCES WERE TAKEN FROM THE GLUCS [11] 2925 1451 435 CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL- 2925 1451 436 TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS 2925 1451 437 SECTIONS [12]. 2925 1451 438 2925 1451 439 **************************************************************** 2925 1451 440 2925 1451 441 REFERENCES: 2925 1451 442 2925 1451 443 [1] F.G. Perey, computer code GENOA, ORNL, unpublished (1967) 2925 1451 444 [2] P.D. Kunz, "Distorted Wave Code DWUCK72," Univ. of 2925 1451 445 Colorado, unpublished (1972) 2925 1451 446 [3] C.Y. Fu, report ORNL/TM-7042 (1980); also, C.Y Fu, 2925 1451 447 Symp. on Neutron Cross Sections from 10 to 50 MeV, Upton, NY,2925 1451 448 May 1980, Brookhaven National Lab. report BNL-NCS-51245 2925 1451 449 (1980) p.675 2925 1451 450 [4] K. Shibata and C.Y. Fu, report ORNL/TM-10093 (1986) 2925 1451 451 [5] D.M. Hetrick, C.Y. Fu, and D.C. Larson, Oak Ridge report 2925 1451 452 ORNL/TM-9083 [ENDF-337] (1984) 2925 1451 453 [6] S.F. Mughabghab, M. Divadeenam, and N.E. Holden, "Neutron 2925 1451 454 Cross Sections, Vol. 1, Neutron Resonance Parameters and 2925 1451 455 Thermal Cross Sections, Part A, Z=1-60," (Academic Press, 2925 1451 456 1981) 2925 1451 457 [7] M.S. Pandey, J.B. Garg and J.A. Harvey, Phys.Rev. C 15, 600 2925 1451 458 (1977), and private communication. 2925 1451 459 [8] F.G. Perey, private communication (1977) 2925 1451 460 [9] D.C. Larson, Symp. on Neutron Cross Sections from 10 to 50 2925 1451 461 MeV, Upton, NY, May 1980, Brookhaven National Lab. report 2925 1451 462 BNL-NCS-51245 (1980) p.277 2925 1451 463 [10] P. Guenther, D.L. Smith, A.B. Smith and J.F. Whalen, Nucl. 2925 1451 464 Phys. A, 448, 280 (1986) [CSISRS data set 12869/002], and 2925 1451 465 W.P. Poenitz and J.F. Whalen, Argonne report ANL/NDM-80 2925 1451 466 (1983) [CSISRS data set 12853] 2925 1451 467 [11] D.M. Hetrick and C.Y. Fu, Oak Ridge report ORNL/TM-7341 2925 1451 468 [ENDF-303] (1980) 2925 1451 469 [12] C.Y. Fu and D.M. Hetrick, Proc. Fourth ASTM-Euratom Symp. 2925 1451 470 on Reactor Dosimetry, Gaithersburg, Maryland, March 22-26, 2925 1451 471 1982 (U.S. National Bureau of Standards) p.877 2925 1451 472 [13] CSISRS Library, National Nuclear Data Center, Brookhaven 2925 1451 473 National Laboratory, Upton, N.Y. 11973. 2925 1451 474 [14] V. McLane, C.L. Dunford and P.F. Rose, "Neutron Cross 2925 1451 475 Sections, Vol. 2, Neutron Cross Section Curves" (Academic 2925 1451 476 Press, 1988) 2925 1451 477 [15] S.M. Qaim, Radiochimica Acta, 25, 13 (1978) 2925 1451 478 [16] M.G. Delfini, J. Kopecky, R.E. Chrien et al., Nucl.Phys. 2925 1451 479 A404, 250 (1983) 2925 1451 480 2925 1451 481 ************************ C O N T E N T S *********************** 2925 1451 482 ***************** Program LINEAR (VERSION 2004-1) ***************2925 1451 483 For All Data Greater than 1.0000E-10 barns in Absolute Value 2925 1451 484 Data Linearized to Within an Accuracy of .100000000 per-cent 2925 1451 485 ***************** Program RECENT (VERSION 2004-1) ***************2925 1451 486 for All Data Greater than 1.0000E-10 barns in Absolute Value 2925 1451 487 Data Linearized to within an Accuracy of .100000000 per-cent 2925 1451 488 ***************** Program FIXUP (Version 2004-1) ****************2925 1451 489 Corrected ZA/AWR in All Sections-----------------------------Yes 2925 1451 490 Corrected Thresholds-----------------------------------------No 2925 1451 491 Extended Cross Sections to 20 MeV----------------------------No 2925 1451 492 Allow Cross Section Deletion---------------------------------No 2925 1451 493 Allow Cross Section Reconstruction---------------------------Yes 2925 1451 494 Make All Cross Sections Non-Negative-------------------------Yes 2925 1451 495 Delete Energies Not in Ascending Order-----------------------Yes 2925 1451 496 Deleted Duplicate Points-------------------------------------Yes 2925 1451 497 Check for Ascending MAT/MF/MT Order--------------------------Yes 2925 1451 498 Check for Legal MF/MT Numbers--------------------------------Yes 2925 1451 499 Allow Creation of Missing Sections---------------------------No 2925 1451 500 Allow Insertion of Energy Points-----------------------------No 2925 1451 501 Create Uniform Energy Grid-----------------------------------No 2925 1451 502 Delete Section if Cross Section =0 at All Energies-----------Yes 2925 1451 503 **************** Program DICTIN (VERSION 2004-1) ****************2925 1451 504 1 451 654 52925 1451 505 2 151 260 12925 1451 506 3 1 25607 42925 1451 507 3 2 25585 42925 1451 508 3 3 24471 42925 1451 509 3 4 20 12925 1451 510 3 5 10 42925 1451 511 3 16 10 12925 1451 512 3 22 8 12925 1451 513 3 28 8 12925 1451 514 3 51 13 12925 1451 515 3 52 12 12925 1451 516 3 53 11 12925 1451 517 3 54 11 12925 1451 518 3 55 11 12925 1451 519 3 56 11 12925 1451 520 3 57 10 12925 1451 521 3 58 10 12925 1451 522 3 59 11 12925 1451 523 3 60 10 12925 1451 524 3 61 10 12925 1451 525 3 62 10 12925 1451 526 3 63 10 12925 1451 527 3 64 10 12925 1451 528 3 65 9 12925 1451 529 3 66 10 12925 1451 530 3 67 10 12925 1451 531 3 68 10 12925 1451 532 3 69 9 12925 1451 533 3 70 10 12925 1451 534 3 71 10 12925 1451 535 3 72 10 12925 1451 536 3 91 9 12925 1451 537 3 102 24439 52925 1451 538 3 103 13 12925 1451 539 3 104 7 12925 1451 540 3 106 6 12925 1451 541 3 107 18 12925 1451 542 4 2 737 42925 1451 543 6 5 13691 42925 1451 544 6 16 364 12925 1451 545 6 22 500 12925 1451 546 6 28 645 12925 1451 547 6 51 41 12925 1451 548 6 52 41 12925 1451 549 6 53 41 12925 1451 550 6 54 41 12925 1451 551 6 55 7 12925 1451 552 6 56 7 12925 1451 553 6 57 7 12925 1451 554 6 58 7 12925 1451 555 6 59 7 12925 1451 556 6 60 7 12925 1451 557 6 61 7 12925 1451 558 6 62 7 12925 1451 559 6 63 7 12925 1451 560 6 64 7 12925 1451 561 6 65 41 32925 1451 562 6 66 7 12925 1451 563 6 67 7 12925 1451 564 6 68 7 12925 1451 565 6 69 7 12925 1451 566 6 70 7 12925 1451 567 6 71 7 12925 1451 568 6 72 7 12925 1451 569 6 91 1489 12925 1451 570 6 103 1143 12925 1451 571 6 107 1079 12925 1451 572 12 51 3 12925 1451 573 12 52 3 12925 1451 574 12 53 3 12925 1451 575 12 54 3 12925 1451 576 12 55 3 12925 1451 577 12 56 3 12925 1451 578 12 57 3 12925 1451 579 12 58 3 12925 1451 580 12 59 4 12925 1451 581 12 60 3 12925 1451 582 12 61 3 12925 1451 583 12 62 4 12925 1451 584 12 63 4 12925 1451 585 12 64 3 12925 1451 586 12 65 3 12925 1451 587 12 66 5 12925 1451 588 12 67 4 12925 1451 589 12 68 4 12925 1451 590 12 69 4 12925 1451 591 12 70 3 12925 1451 592 12 71 3 12925 1451 593 12 72 3 12925 1451 594 12 102 982 52925 1451 595 14 51 1 12925 1451 596 14 52 1 12925 1451 597 14 53 1 12925 1451 598 14 54 1 12925 1451 599 14 55 1 12925 1451 600 14 56 1 12925 1451 601 14 57 1 12925 1451 602 14 58 1 12925 1451 603 14 59 1 12925 1451 604 14 60 1 12925 1451 605 14 61 1 12925 1451 606 14 62 1 12925 1451 607 14 63 1 12925 1451 608 14 64 1 12925 1451 609 14 65 1 12925 1451 610 14 66 1 12925 1451 611 14 67 1 12925 1451 612 14 68 1 12925 1451 613 14 69 1 12925 1451 614 14 70 1 12925 1451 615 14 71 1 12925 1451 616 14 72 1 12925 1451 617 14 102 1 52925 1451 618 15 102 90 12925 1451 619 33 1 22 12925 1451 620 33 2 14 12925 1451 621 33 3 18 12925 1451 622 33 4 9 12925 1451 623 33 16 58 12925 1451 624 33 22 16 12925 1451 625 33 28 14 12925 1451 626 33 51 12 12925 1451 627 33 52 12 12925 1451 628 33 53 12 12925 1451 629 33 54 12 12925 1451 630 33 55 12 12925 1451 631 33 56 12 12925 1451 632 33 57 12 12925 1451 633 33 58 12 12925 1451 634 33 59 12 12925 1451 635 33 60 12 12925 1451 636 33 61 12 12925 1451 637 33 62 12 12925 1451 638 33 63 12 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