28-Ni- 62 ENDF/B-VI, Processed by Red Cullen using PREPRO2004 6000 0 0 0 2.80620E+4 6.13960E+1 2 0 0 52837 1451 1 0.0 0.0 0 0 0 62837 1451 2 1.00000E+0 1.50000E+8 8 5 10 62837 1451 3 0.0 0.0 1 0 469 582837 1451 4 28-Ni- 62 LANL,ORNL EVAL-SEP97 S.CHIBA,M.B.CHADWICK,HETRICK 2837 1451 5 Ch97,Ch99 DIST-SEP 1 REV4- 20010926 2837 1451 6 ----ENDF/B-VI MATERIAL 2837 REVISION 3 2837 1451 7 -----INCIDENT NEUTRON DATA 2837 1451 8 ------ENDF-6 FORMAT 2837 1451 9 2837 1451 10 **************************************************************** 2837 1451 11 2837 1451 12 ENDF/B-VI MOD 5 Revision, June 2000, S.C. Frankle, R.C. Reedy, 2837 1451 13 P.G. Young (LANL) 2837 1451 14 2837 1451 15 The secondary gamma-ray spectrum for radiative capture (MF 12, 2837 1451 16 MT 102) has been updated for new experimental data at incident 2837 1451 17 neutron energies up to 1 keV. 2837 1451 18 The MF=12, MT=102 yields above 1 keV were adjusted slightly to 2837 1451 19 force energy conservation. 2837 1451 20 The Q-value for radiative capture was also updated in File 3. 2837 1451 21 Details of these changes are described in Frankel et al. [Fr01]. 2837 1451 22 2837 1451 23 **************************************************************** 2837 1451 24 2837 1451 25 ENDF/B-VI MOD 4 Evaluation, September 1997, S. Chiba, 2837 1451 26 M.B. Chadwick, P.G. Young (LANL), and 2837 1451 27 A.J. Koning (ECN) 2837 1451 28 2837 1451 29 Los Alamos LA150 Library, produced with FKK/GNASH/GSCAN code 2837 1451 30 in cooperation with ECN Petten. 2837 1451 31 2837 1451 32 This evaluation provides a complete representation of the 2837 1451 33 nuclear data needed for transport, damage, heating, 2837 1451 34 radioactivity, and shielding applications over the incident 2837 1451 35 neutron energy range from 1.0E-11 to 150 MeV. The discussion 2837 1451 36 here is divided into the region below and above 20 MeV. 2837 1451 37 2837 1451 38 INCIDENT NEUTRON ENERGIES < 20 MeV 2837 1451 39 2837 1451 40 Below 20 MeV the evaluation is based completely on the ENDF/B- 2837 1451 41 VI (MOD3) evaluation by Larson, C. Perey, Hetrick, and 2837 1451 42 Fu. 2837 1451 43 2837 1451 44 INCIDENT NEUTRON ENERGIES > 20 MeV 2837 1451 45 2837 1451 46 The ENDF/B-VI Release 2 evaluation extends to 20 MeV and 2837 1451 47 includes cross sections and energy-angle data for all 2837 1451 48 significant reactions. The present evaluation utilizes a more 2837 1451 49 compact composite reaction spectrum representation above 20 MeV 2837 1451 50 in order to reduce the length of the file. No essential data for 2837 1451 51 applications is lost with this representation. 2837 1451 52 The evaluation above 20 MeV utilizes MF=6, MT=5 to represent 2837 1451 53 all reaction data. Production cross sections and emission 2837 1451 54 spectra are given for neutrons, protons, deuterons, tritons, 2837 1451 55 alpha particles, gamma rays, and all residual nuclides produced 2837 1451 56 (A>5) in the reaction chains. To summarize, the ENDF sections 2837 1451 57 with non-zero data above En = 20 MeV are: 2837 1451 58 2837 1451 59 MF=3 MT= 1 Total Cross Section 2837 1451 60 MT= 2 Elastic Scattering Cross Section 2837 1451 61 MT= 3 Nonelastic Cross Section 2837 1451 62 MT= 5 Sum of Binary (n,n') and (n,x) Reactions 2837 1451 63 2837 1451 64 MF=4 MT= 2 Elastic Angular Distributions 2837 1451 65 2837 1451 66 MF=6 MT= 5 Production Cross Sections and Energy-Angle 2837 1451 67 Distributions for Emission Neutrons, Protons, 2837 1451 68 Deuterons, Tritons, and Alphas; and Angle- 2837 1451 69 Integrated Spectra for Gamma Rays and Residual 2837 1451 70 Nuclei That Are Stable Against Particle Emission 2837 1451 71 2837 1451 72 The evaluation is based on nuclear model calculations that 2837 1451 73 have been benchmarked to experimental data, especially for n + 2837 1451 74 Ni58 and p + Ni58 reactions [Ch97]. We use the GNASH code system 2837 1451 75 [Yo92], which utilizes Hauser-Feshbach statistical, 2837 1451 76 preequilibrium and direct-reaction theories. Spherical optical 2837 1451 77 model calculations are used to obtain particle transmission 2837 1451 78 coefficients for the Hauser-Feshbach calculations, as well as 2837 1451 79 for the elastic neutron angular distributions. 2837 1451 80 Cross sections and spectra for producing individual residual 2837 1451 81 nuclei are included for reactions. The energy-angle-correlations 2837 1451 82 for all outgoing particles are based on Kalbach systematics 2837 1451 83 [Ka88]. 2837 1451 84 A model was developed to calculate the energy distributions of 2837 1451 85 all recoil nuclei in the GNASH calculations [Ch96]. The recoil 2837 1451 86 energy distributions are represented in the laboratory system in 2837 1451 87 MT=5, MF=6, and are given as isotropic in the lab system. All 2837 1451 88 other data in MT=5,MF=6 are given in the center-of-mass system. 2837 1451 89 This method of representation utilizes the LCT=3 option approved 2837 1451 90 at the November, 1996, CSEWG meeting. 2837 1451 91 Preequilibrium corrections were performed in the course of the 2837 1451 92 GNASH calculations using the exciton model of Kalbach [Ka77, 2837 1451 93 Ka85], validated by comparison with calculations using Feshbach, 2837 1451 94 Kerman, Koonin (FKK) theory [Ch93]. Discrete level data from 2837 1451 95 nuclear data sheets were matched to continuum level densities 2837 1451 96 using the formulation of Gilbert and Cameron [Gi65] and pairing 2837 1451 97 and shell parameters from the Cook [Co67] analysis. Neutron and 2837 1451 98 charged- particle transmission coefficients were obtained from 2837 1451 99 the optical potentials, as discussed below. Gamma-ray 2837 1451 100 transmission coefficients were calculated using the Kopecky-Uhl 2837 1451 101 model [Ko90]. 2837 1451 102 2837 1451 103 SOME Ni-SPECIFIC INFORMATION CONCERNING THE EVAL. 2837 1451 104 2837 1451 105 The neutron total cross section was evaluated based on the 2837 1451 106 least-squares method with GMA code system [Po81] taking account of2837 1451 107 the experimental data [Ci68, Pe73, Sc73, La83, Di97, Fa66, Du67]. 2837 1451 108 The data for natural Ni were also used because there was not 2837 1451 109 enough data for Ni-62 above 20 MeV. The data for natural Ni were 2837 1451 110 transformed to the Ni-62 cross section according to A*(2/3) law. 2837 1451 111 In the GMA analysis, the systematic error was assumed to be 1 % 2837 1451 112 for all the data set. Result of the GMA evaluation was used as 2837 1451 113 the evaluated total cross section data above 20 MeV. 2837 1451 114 2837 1451 115 The evaluated total cross section data (1 to 250 MeV) and s-wave 2837 1451 116 strength function [Mu81] were used to obtain the neutron optical 2837 1451 117 potential parameters. The parameter estimation was carried out 2837 1451 118 based on Marquart-Bayesian approach [Sm91], where ECIS95 code was 2837 1451 119 used for the optical model calculation. We have employed the 2837 1451 120 energy dependence of the optical potential similar to Delaroche's 2837 1451 121 work [De89]. The initial potential parameters were adopted from 2837 1451 122 Koning and Delaroche [Ko97]. Total of 7 parameters concerning the2837 1451 123 central potential depth were estimated with associated covariance 2837 1451 124 matrix, while the geometrical parameters were fixed to the result 2837 1451 125 of a similar search for n + Ni-58. Presently obtained potential 2837 1451 126 was used for the calculation of neutron transmission coefficients 2837 1451 127 and DWBA cross sections in the energy region above 20 MeV. Below 2837 1451 128 20 MeV, the Harper neutron potential [Ha82] was used for the 2837 1451 129 calculation of transmission coefficients. 2837 1451 130 2837 1451 131 The proton optical potential was also searched for to obtain a 2837 1451 132 good description of proton-total reaction cross section as 2837 1451 133 predicted by Wellisch-Axen systematic [We96] above 50 MeV. The 2837 1451 134 parameter estimation was carried out by the Marquart-Bayesian 2837 1451 135 approach similar to the neutron OMP, but trying to seek the best 2837 1451 136 parameter to reproduce the reaction cross sections compiled by 2837 1451 137 Carlson [Ca96] and Wellisch values. The experimental data in 2837 1451 138 Carlson [Ca96] was scaled for Ni-62 according to A**(2/3) law. In2837 1451 139 this search, the geometrical parameters were fixed to be same as 2837 1451 140 the neutron potential. The present potential gives a good 2837 1451 141 description of the proton total reaction cross section from 10 MeV2837 1451 142 to 250 MeV. However, after some trial and error to reproduce both2837 1451 143 the elastic scattering and reaction cross section data for Ni-58, 2837 1451 144 we have employed the following combination of proton potentials: 2837 1451 145 2837 1451 146 0 to 5 MeV : Harper potential [Ha82] 2837 1451 147 6 to 47 MeV : Koning and Delaroche [Ko97] 2837 1451 148 48 to 260 MeV : Present OMP 2837 1451 149 2837 1451 150 For deuterons, the Lohr-Haeberli [Lo74] global potential was used;2837 1451 151 for alpha particles the McFadden-Satchler [Mc66] potential was 2837 1451 152 used; and for tritons the Becchetti-Greenlees [Be71] potential was2837 1451 153 used. The He-3 channel was ignored. 2837 1451 154 2837 1451 155 The direct collective inelastic scattering to the following levels2837 1451 156 in Ni-62 was considered by the DWBA-mode calculation of ECIS95: 2837 1451 157 2837 1451 158 Jpi Ex(MeV) Deformation length 2837 1451 159 2+ 1.173 1.008 2837 1451 160 3- 3.757 0.83 2837 1451 161 2837 1451 162 The data for the 2+ level was retrieved from the literature 2837 1451 163 [Ra87]. The data for the 3- level was estimated to be an average 2837 1451 164 of the same quantity for Ni-58 and Ni-60. 2837 1451 165 2837 1451 166 **************************************************************** 2837 1451 167 2837 1451 168 REFERENCES 2837 1451 169 2837 1451 170 [Be71] F.D. Becchetti, Jr., and G.W. Greenlees in 2837 1451 171 "Polarization Phenomena in Nuclear Reactions," (Ed: H.H. 2837 1451 172 Barschall and W. Haeberli, The University of Wisconsin Press, 2837 1451 173 1971) p.682 2837 1451 174 [Bo71] P. Boschung et al, Nucl.Phys. A161, 593 (1971) 2837 1451 175 [Ca96] R.F. Carlson, Atomic Data and Nuclear Data Tables, 63, 2837 1451 176 93 (1996) 2837 1451 177 [Ch93] M.B. Chadwick and P.G. Young, Phys.Rev. C 47, 2255 (1993) 2837 1451 178 [Ch96] M.B. Chadwick, P.G. Young, R.E. MacFarlane, and A.J. 2837 1451 179 Koning, "High-Energy Nuclear Data Libraries for Accelerator- 2837 1451 180 Driven Technologies: Calculational Method for Heavy Recoils," 2837 1451 181 Proc. of 2nd Int. Conf. on Accelerator Driven Transmutation 2837 1451 182 Technology and Applications, Kalmar, Sweden, 3-7 June 1996 2837 1451 183 [Ch97] M. B. Chadwick and P. G. Young, "Model Calculations of 2837 1451 184 n,p + 58,60,61,62,64Ni" in APT PROGRESS REPORT: 1 August - 1 2837 1451 185 September 1997, internal Los Alamos National Laboratory memo T-2837 1451 186 2-97/MS-51, 8 September 1997 from R.E. MacFarlane to L. Waters.2837 1451 187 [Ch99] M.B. Chadwick, P G. Young, G. M. Hale, et al., Los Alamos 2837 1451 188 National Laboratory report, LA-UR-99-1222 (1999) 2837 1451 189 [Ci68] S. Cierjack et al, report KFK-1000 (1968) 2837 1451 190 [Co67] J.L. Cook, H. Ferguson, and A.R. DeL Musgrove, Aust.J. 2837 1451 191 Phys. 20, 477 (1967) 2837 1451 192 [De89] J.P. Delaroche, Y. Wang and J. Rapaport, Phys.Rev.C 39, 2837 1451 193 391 (1989) 2837 1451 194 [Di97] F. Dietrich et al., private communication (1997). 2837 1451 195 [Du67] Yu.V. Dukarevich et al., Nucl.Phys. A92, 433 (1967) 2837 1451 196 [Fa66] J.A. Farrel et al, Ann.Phys. 36, 367 (1966) 2837 1451 197 [Fe80] M.B. Fedorov et al., 80Kiev, 1, 309(1980) 2837 1451 198 [Fr01] S.C. Frankle, R.C. Reedy, and P.G. Young, Los ALamos 2837 1451 199 National Laboratory Report, LA-13812 (2001). 2837 1451 200 [Gi65] A. Gilbert and A.G.W. Cameron, Can.J.Phys. 43, 1446 (1965)2837 1451 201 [Gu85] P.P. Guss et al, Nucl.Phys. A438, 187 (1985) 2837 1451 202 [Ha82] R.C. Harper and W.L. Alford, J.Phys.G. 8, 153 (1982) 2837 1451 203 [Ka77] C. Kalbach, Z.Phys.A 283, 401 (1977) 2837 1451 204 [Ka85] C. Kalbach, Los Alamos National Laboratory report 2837 1451 205 LA-10248-MS (1985) 2837 1451 206 [Ka88] C. Kalbach, Phys.Rev.C 37, 2350 (1988); see also 2837 1451 207 C. Kalbach and F. M. Mann, Phys.Rev.C 23, 112 (1981) 2837 1451 208 [Ko90] J. Kopecky and M. Uhl, Phys.Rev.C 41, 1941 (1990) 2837 1451 209 [Ko97] A. Koning and J.P. Delaroche, private communication. 2837 1451 210 [La83] D.C. Larson et al, report ORNL-TM-8203 (1983) 2837 1451 211 [Lo74] J.M.Lohr and W.Haeberli, Nucl.Phys. A232, 381 (1974) 2837 1451 212 [Mc66] L. McFadden and G.R. Satchler, Nucl.Phys. 84, 177 (1966) 2837 1451 213 [Mu81] S.F. Mughabghab, M. Divadeenam and N.E. Holden, "Neutron 2837 1451 214 Cross Sections", Vol. 1, Part A (Academic Press, 1981) 2837 1451 215 [Pe73] F.G. Perey, private communication (1973) [EXFOR 10342] 2837 1451 216 [Pe82] C.M. Perey et al, Oak Ridge report ORNL-5893 (1982) 2837 1451 217 [Pe88] Pedroni et al, Phys.Rev.C 38, 2052 (1988) 2837 1451 218 [Po81] W. Poenitz, Nuclear Data Evaluation Methods and 2837 1451 219 and Procedures, Proc. Conf., Upton, NY, 1981, Brookhaven Report2837 1451 220 BNL-NCS-51363 (1981) p. 249 2837 1451 221 [Ra87] S. Raman et al, At. Data Nucl. Data Tables, 36, 1(1987). 2837 1451 222 [Ra96] J. Raynal, "Notes on ECIS94", Service de Physique 2837 1451 223 Theorique, Saclay, France (personal communication through A.J. 2837 1451 224 Koning, 1996). 2837 1451 225 [Sc73] W. Schimmerling et al., Phys.Rev.C 7, 248 (1973) 2837 1451 226 [Sm79] A.B. Smith et al., Nucl.Sci.Eng., 72, 293 (1979) 2837 1451 227 [Sm91] D.L. Smith, "Probability, Statistics, and Data Uncertainty2837 1451 228 in Nuclear Science and Technology" (American Nuclear Society, 2837 1451 229 1991) 2837 1451 230 [We96] H.P. Wellisch and D. Axen, Phys.Rev.C 54, 1329 (1996) 2837 1451 231 [Yo92] P.G. Young, E.D. Arthur, and M.B. Chadwick, Los Alamos 2837 1451 232 report LA-12343-MS (1992) 2837 1451 233 2837 1451 234 **************************************************************** 2837 1451 235 2837 1451 236 ENDF/B-VI MOD 3 Revision, October 1997, V. McLane (NNDC) 2837 1451 237 2837 1451 238 1. Corrected residual nucleus in File 6, MT=22, and exponent for 2837 1451 239 alpha in MT=28. 2837 1451 240 2. Updated File 1 comments and corrected references. 2837 1451 241 2837 1451 242 **************************************************************** 2837 1451 243 2837 1451 244 ENDF/B-VI MOD 2 Revision, July 1991, 2837 1451 245 D.M. Hetrick, C.Y. Fu, N.M. Larson (ORNL) 2837 1451 246 2837 1451 247 1. The secondary particle distributions for MF=6, MT=51-54 were 2837 1451 248 corrected-to-center of mass from laboratory coordinates. 2837 1451 249 2. The elastic transformation matrix was removed. 2837 1451 250 2837 1451 251 ******************************************************************2837 1451 252 2837 1451 253 ENDF/B-VI MOD 1 Evaluation, November 1989, 2837 1451 254 D.M. Hetrick, C.Y. Fu, N.M. Larson (ORNL) 2837 1451 255 2837 1451 256 This work employed the Hauser-Feshbach code TNG [1,2,3]. 2837 1451 257 The TNG code provides energy and angular distributions of 2837 1451 258 particles emitted in the compound and pre-compound reactions, 2837 1451 259 ensures consistency among all reactions, and maintains energy 2837 1451 260 balance. Details pertinent to the contents of this evaluation 2837 1451 261 can be found in Hetrick et al. [4]. 2837 1451 262 2837 1451 263 DESCRIPTION OF FILES 2837 1451 264 2837 1451 265 File 1: GENERAL INFORMATION ------------------------------------ 2837 1451 266 MT=451 General information, references, and definitions. 2837 1451 267 2837 1451 268 File 2 RESONANCE PARAMETERS ------------------------------------ 2837 1451 269 MT=151 Resonance Parameters; taken from the compilation 2837 1451 270 of Mughabghab [5]. From 1.E-5 eV to 600 keV the scattering 2837 1451 271 cross section is given completely by the resonance 2837 1451 272 parameters. For total and capture, a contribution is added 2837 1451 273 from 10-600 keV due to the capture cross section (see File 3,2837 1451 274 MT=102 below). No background files are given. 2837 1451 275 2837 1451 276 Thermal cross sections values (barns): 2837 1451 277 Total 24.3 2837 1451 278 Elastic scattering 9.89 2837 1451 279 Capture 14.4 2837 1451 280 2837 1451 281 Note that the flag has been set to allow user calculation 2837 1451 282 of the angular distributions from the R-Matrix resonance 2837 1451 283 parameters, if the user wants angular distributions on a 2837 1451 284 finer energy grid than given in File 4, MT=2. 2837 1451 285 2837 1451 286 File 3 CROSS SECTIONS ------------------------------------------ 2837 1451 287 MT=1 Total cross section - 1.E-5 eV to 600 keV, given by 2837 1451 288 resonance parameters and a contribution from 10 to 600 keV 2837 1451 289 which supplements the resonance capture. From 600 keV to 2837 1451 290 20 MeV, natural Ni data of Larson et al. [6] were used as 2837 1451 291 no 62Ni data were available. 2837 1451 292 MT=2 Elastic scattering cross sections were obtained by 2837 1451 293 subtracting the nonelastic from the total. 2837 1451 294 MT=3 Nonelastic cross section; sum of MT=4,16,22,28,102-104, 2837 1451 295 and 107. 2837 1451 296 MT=4 Total inelastic cross section; sum of MT=51-54 and 91. 2837 1451 297 MT=16 (n,2n) cross sections were calculated by the TNG code 2837 1451 298 [1,2,3,4]. No data available. 2837 1451 299 MT=22 (n,na) cross sections were calculated by the TNG code 2837 1451 300 [1,2,3,4]. No data available other than alpha emission. 2837 1451 301 MT=28 (n,np)+(n,pn) cross sections were calculated by the TNG 2837 1451 302 code [1,2,3,4]. Available data disagree, but data of Qaim 2837 1451 303 [7] for (n,np)+(n,pn) includes (n,d). Thus, ENDF/B-V natural 2837 1451 304 Ni (n,d) data [8] was normalized so that the TNG calculated 2837 1451 305 for (n,np)+(n,pn), + the (n,d) value, fit the Qaim data for 2837 1451 306 (n,np)+(n,pn)+(n,d). 2837 1451 307 MT=51-54 Inelastic scattering exciting levels; results are 2837 1451 308 from TNG [1,2,3,4]. 2837 1451 309 MT=91 Inelastic scattering exciting the continuum (TNG 2837 1451 310 calculated). 2837 1451 311 MT=102 (n,gamma) capture cross section given by resonance 2837 1451 312 parameters from 1.E-5 eV to 10 keV. While the resonance 2837 1451 313 parameters contribute up to 600 keV, an additional 2837 1451 314 contribution from TNG is included from 10 to 600 keV, due to 2837 1451 315 incomplete experimental capture resonance information. The 2837 1451 316 same normalization (0.4) used for 58,60Ni was assumed for 2837 1451 317 62Ni; the normalized TNG calculations were used from 600 keV 2837 1451 318 to 20 MeV. 2837 1451 319 MT=103 (n,p) cross sections were calculated by the TNG code 2837 1451 320 [1,2,3,4]. 2837 1451 321 MT=104 (n,d) cross sections were taken from the ENDF/B-V file 2837 1451 322 [8] for natural Ni but normalized to be smaller by a factor 2837 1451 323 of 5.5 so that the (n,np)+(n,pn)+(n,d) cross section matched 2837 1451 324 the data of Qaim [7]. 2837 1451 325 MT=107 (n,a) cross sections were taken from the ENDF/B-V 2837 1451 326 activation file but normalized to be smaller by a factor of 2837 1451 327 1.9 so that the cross sections fit the available data of 2837 1451 328 Qaim et al. [9] and Kneff et al [10]. 2837 1451 329 2837 1451 330 File 4: ANGULAR DISTRUTIONS ------------------------------------ 2837 1451 331 MT=2 Angular distributions of secondary neutrons given for 2837 1451 332 elastic scattering are from ENDF/B-V. 2837 1451 333 If desired, angular distributions can be calculated by 2837 1451 334 the user on a finer energy grid from the R-Matrix resonance 2837 1451 335 parameters in File 2, MT=151. 2837 1451 336 2837 1451 337 File 6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS --------------------- 2837 1451 338 MT=16 (n,2n) reaction; includes simple constant yields for 2837 1451 339 the neutron and 61Ni residual, and energy dependent yield 2837 1451 340 based on TNG calculated gamma-ray spectra for the gamma ray;2837 1451 341 TNG calculated normalized distributions are given for each 2837 1451 342 product. Isotropy is assumed. 2837 1451 343 MT=22 (n,na)+(n,an); includes simple constant yields for the 2837 1451 344 neutron, alpha, and 58Fe residual, and energy dependent 2837 1451 345 yield based on the TNG calculated gamma-ray spectra for the 2837 1451 346 gamma ray; calculated normalized distributions are given 2837 1451 347 for each product. Isotropy is assumed. 2837 1451 348 MT=28 (n,np)+(n,pn); includes simple constant yields for the 2837 1451 349 neutron, proton, and 61Co residual, and energy dependent 2837 1451 350 yield based on TNG calculated gamma-ray spectra for the 2837 1451 351 gamma ray; calculated normalized distributions are given 2837 1451 352 for each product. Isotropy is assumed. 2837 1451 353 MT=51 through 54 Inelastic scattering exciting levels; 2837 1451 354 assumed isotropic. 2837 1451 355 MT=91 Inelastic scattering exciting the continuum; includes 2837 1451 356 simple constant yields for the neutron and 62Ni residual 2837 1451 357 and energy dependent yield based on TNG calculated gamma- 2837 1451 358 ray spectra for the gamma ray; TNG calculated normalized 2837 1451 359 distributions are given for each. Isotropy is assumed. 2837 1451 360 MT=103 (n,p) reaction; includes simple constant yields for 2837 1451 361 proton and 62Co residual, and energy dependent yield based 2837 1451 362 on calculated gamma-ray spectra for gamma ray; calculated 2837 1451 363 normalized distributions are given for each product. 2837 1451 364 Isotropy is assumed. 2837 1451 365 MT=107 (n,a) reaction; includes simple constant yields for 2837 1451 366 alpha and 59Fe residual, and energy dependent yield based 2837 1451 367 on calculated gamma-ray spectra for gamma ray; calculated 2837 1451 368 calculated normalized distributions are given for each 2837 1451 369 product. Isotropy is assumed. 2837 1451 370 2837 1451 371 File 12: PHOTON PRODUCTION MULTIPLICITIES ---------------------- 2837 1451 372 MT=51 through 54 Branching ratios for the levels are given. 2837 1451 373 MT=102 (n,g) capture; multiplicities for energies less than 2837 1451 374 1.0 MeV were taken from ENDF/B-V, but adjusted for energy 2837 1451 375 balance; TNG calculations were used for En = 2 and 5 MeV. 2837 1451 376 2837 1451 377 File 14: PHOTON ANGULAR DISTRIBUTIONS -------------------------- 2837 1451 378 MT=51 through 54 and 102 Gamma ray angular distributions 2837 1451 379 assumed to be isotropic. 2837 1451 380 2837 1451 381 File 15: CONTINUOUS PHOTON ENERGY SPECTRA ---------------------- 2837 1451 382 MT=102 (n,g) capture; as in File 12, MT=102. 2837 1451 383 2837 1451 384 File 33: UNCERTAINTY FILES ------------------------------------ 2837 1451 385 An LB=8 section is included for all non-derived files as 2837 1451 386 required by ENDF/B-VI. 2837 1451 387 2837 1451 388 MT=1 Uncertainties are derived from 1.E-5 to 10 eV. From 10 2837 1451 389 Ev to 20 MeV they are explicit, using LB=0,1 and 8. 2837 1451 390 MT=2 From 1.E-5 to 10 eV, uncertainties are explicit, based 2837 1451 391 upon thermal uncertainty and other data. From 10 eV to 20 2837 1451 392 MeV the files are derived. 2837 1451 393 MT=3 From 1.E-5 to 600 keV uncertainties are derived. 2837 1451 394 From 600 keV to 20 MeV uncertainties are explicit, using 2837 1451 395 LB=1 and 8. 2837 1451 396 MT=4 Uncertainties are all derived. 2837 1451 397 MT=16 Uncertainties for (n,2n) are explicit, estimated from 2837 1451 398 TNG. 2837 1451 399 MT=22 Uncertainties for (n,na) are explicit, estimated from 2837 1451 400 TNG. 2837 1451 401 MT=28 Uncertainties for (n,np) are explicit, estimated from 2837 1451 402 TNG. 2837 1451 403 MT=51 through91 Uncertainties for inelastic scattering are 2837 1451 404 explicit, based on data and calculation uncertainties. 2837 1451 405 MT=102 Uncertainties are explicit, based on thermal data at 2837 1451 406 low energies, and calculated results above 600 keV. 2837 1451 407 MT=103 Uncertainties estimated from TNG. 2837 1451 408 MT=104 Uncertainties estimated, based on data. 2837 1451 409 MT=107 Uncertainties estimated from TNG. 2837 1451 410 2837 1451 411 **************************************************************** 2837 1451 412 2837 1451 413 REFERENCES 2837 1451 414 2837 1451 415 [1] C.Y. Fu, "A Consistent Nuclear Model for Compound and 2837 1451 416 Precompound Reactions with Conservation of Angular 2837 1451 417 Momentum," Oak Ridge National Laboratory report ORNL/TM-7042 2837 1451 418 (1980). 2837 1451 419 [2] C.Y Fu, "Development and Application of Multi-Step 2837 1451 420 Hauser-Feshbach/Pre-equilibrium Model Theory," Symp. 2837 1451 421 Neutron Cross Sections from 10 to 50 MeV, Upton, N.Y., 2837 1451 422 May 12-14, 1980, Brookhaven National Laboratory report 2837 1451 423 BNL-NCS-51425, P 675 2837 1451 424 [3] K. Shibata and C.Y. Fu, "Recent Improvements of the TNG 2837 1451 425 Statistical Model Code", Oak Ridge National Laboratory 2837 1451 426 report ORNL/TM-10093 (1986). 2837 1451 427 [4] D.M. Hetrick, C.Y. Fu, and D.C. Larson, "Calculated Neutron 2837 1451 428 -Induced Cross Sections for 58,60Ni from 1 to 20 MeV and 2837 1451 429 Comparisons with Experiment," Oak Ridge National Laboraotry 2837 1451 430 report ORNL/TM-10219 [ENDF-344] (1987). 2837 1451 431 [5] S.F. Mughabghab, M. Divadeenam, and N.E. Holden, "Neutron 2837 1451 432 Cross Sections, Vol. 1, Neutron Resonance Parameters and 2837 1451 433 Thermal Cross Sections, Part A, Z=1-60," (Academic Press, 2837 1451 434 1981) 2837 1451 435 [6] D.C. Larson, N.M. Larson, J.A. Harvey, N.W. Hill and C.H. 2837 1451 436 Johnson, "Application of New Techniques to ORELA Neutron 2837 1451 437 Transmission Measurements and Their Uncertainty Analysis: 2837 1451 438 the Case of Natural Nickel from 2 keV to 20 MeV", Oak 2837 1451 439 Ridge National Laboratory report ORNL/TM8203 [ENDF-333] 2837 1451 440 (1983) 2837 1451 441 [7] S.M. Qaim, Nucl.Phys. A382, 255 (1982) 2837 1451 442 [8] M. Divadeenam, "Ni Elemental Neutron Induced Reaction Cross 2837 1451 443 Section Evaluation", Brookhaven National Laboratory report 2837 1451 444 BNL-NCS-51346 [ENDF-294] (1979). 2837 1451 445 [9] S.M. Qaim, R. Wolfle, M.M. Rahman, and H. Ollig, Nucl.Sci. 2837 1451 446 Eng. 88, 143 (1984) 2837 1451 447 [10] D.W. Kneff, B.M. Oliver, H. Farrar IV, and L.R. Greenwood, 2837 1451 448 Nucl.Sci.Eng. 92, 491 (1986) 2837 1451 449 2837 1451 450 ************************ C O N T E N T S *********************** 2837 1451 451 ***************** Program LINEAR (VERSION 2004-1) ***************2837 1451 452 For All Data Greater than 1.0000E-10 barns in Absolute Value 2837 1451 453 Data Linearized to Within an Accuracy of .100000000 per-cent 2837 1451 454 ***************** Program RECENT (VERSION 2004-1) ***************2837 1451 455 for All Data Greater than 1.0000E-10 barns in Absolute Value 2837 1451 456 Data Linearized to within an Accuracy of .100000000 per-cent 2837 1451 457 ***************** Program FIXUP (Version 2004-1) ****************2837 1451 458 Corrected ZA/AWR in All Sections-----------------------------Yes 2837 1451 459 Corrected Thresholds-----------------------------------------No 2837 1451 460 Extended Cross Sections to 20 MeV----------------------------No 2837 1451 461 Allow Cross Section Deletion---------------------------------No 2837 1451 462 Allow Cross Section Reconstruction---------------------------Yes 2837 1451 463 Make All Cross Sections Non-Negative-------------------------Yes 2837 1451 464 Delete Energies Not in Ascending Order-----------------------Yes 2837 1451 465 Deleted Duplicate Points-------------------------------------Yes 2837 1451 466 Check for Ascending MAT/MF/MT Order--------------------------Yes 2837 1451 467 Check for Legal MF/MT Numbers--------------------------------Yes 2837 1451 468 Allow Creation of Missing Sections---------------------------No 2837 1451 469 Allow Insertion of Energy Points-----------------------------No 2837 1451 470 Create Uniform Energy Grid-----------------------------------No 2837 1451 471 Delete Section if Cross Section =0 at All Energies-----------Yes 2837 1451 472 **************** Program DICTIN (VERSION 2004-1) ****************2837 1451 473 1 451 531 52837 1451 474 2 151 63 12837 1451 475 3 1 5764 42837 1451 476 3 2 5742 42837 1451 477 3 3 4941 42837 1451 478 3 4 15 12837 1451 479 3 5 9 42837 1451 480 3 16 7 12837 1451 481 3 22 7 12837 1451 482 3 28 6 12837 1451 483 3 51 14 12837 1451 484 3 52 13 12837 1451 485 3 53 12 12837 1451 486 3 54 12 12837 1451 487 3 91 11 12837 1451 488 3 102 4922 52837 1451 489 3 103 10 12837 1451 490 3 104 11 12837 1451 491 3 107 14 12837 1451 492 4 2 3747 42837 1451 493 6 5 12907 42837 1451 494 6 16 280 12837 1451 495 6 22 307 32837 1451 496 6 28 242 32837 1451 497 6 51 7 22837 1451 498 6 52 7 22837 1451 499 6 53 7 22837 1451 500 6 54 7 22837 1451 501 6 91 1023 12837 1451 502 6 103 614 12837 1451 503 6 107 795 12837 1451 504 12 51 3 12837 1451 505 12 52 3 12837 1451 506 12 53 3 12837 1451 507 12 54 3 12837 1451 508 12 102 381 52837 1451 509 14 51 1 12837 1451 510 14 52 1 12837 1451 511 14 53 1 12837 1451 512 14 54 1 12837 1451 513 14 102 1 52837 1451 514 15 102 114 12837 1451 515 33 1 20 12837 1451 516 33 2 14 12837 1451 517 33 3 16 12837 1451 518 33 4 9 12837 1451 519 33 16 14 12837 1451 520 33 22 14 12837 1451 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