28-Ni- 60 ENDF/B-VI, Processed by Red Cullen using PREPRO2004 6000 0 0 0 2.80600E+4 5.94160E+1 2 0 0 42831 1451 1 0.0 0.0 0 0 0 62831 1451 2 1.00000E+0 1.50000E+8 8 0 10 62831 1451 3 0.0 0.0 1 0 486 932831 1451 4 28-Ni- 60 LANL,ORNL EVAL-SEP97 S.CHIBA,M.B.CHADWICK,LARSON 2831 1451 5 Ch97,Ch99 DIST-SEP 1 REV3- 20010926 2831 1451 6 ----ENDF/B-VI MATERIAL 2831 REVISION 2 2831 1451 7 -----INCIDENT NEUTRON DATA 2831 1451 8 ------ENDF-6 FORMAT 2831 1451 9 2831 1451 10 ******************************************************************2831 1451 11 2831 1451 12 ENDF/B-VI MOD 4 Revision, June 2000, S.C. Frankle, R.C. Reedy, 2831 1451 13 P.G. Young (LANL) 2831 1451 14 2831 1451 15 The secondary gamma-ray spectrum for radiative capture (MF 12, 2831 1451 16 MT 102) has been updated for new experimental data at incident 2831 1451 17 neutron energies up to 1 keV. 2831 1451 18 The Q-value for radiative capture was also updated in File 3. 2831 1451 19 Details of these changes are described in Frankel et al. [Fr01]. 2831 1451 20 2831 1451 21 **************************************************************** 2831 1451 22 2831 1451 23 ENDF/B-VI MOD 3 Evaluation, September 1997, S. Chiba, 2831 1451 24 M.B. Chadwick, P.G. Young (LANL), and 2831 1451 25 A.J. Koning (ECN) 2831 1451 26 2831 1451 27 Los Alamos LA150 Library, produced with FKK/GNASH/GSCAN code 2831 1451 28 in cooperation with ECN Petten. 2831 1451 29 2831 1451 30 This evaluation provides a complete representation of the 2831 1451 31 nuclear data needed for transport, damage, heating, 2831 1451 32 radioactivity, and shielding applications over the incident 2831 1451 33 neutron energy range from 1.0E-11 to 150 MeV. The discussion 2831 1451 34 here is divided into the region below and above 20 MeV. 2831 1451 35 2831 1451 36 INCIDENT NEUTRON ENERGIES < 20 MeV 2831 1451 37 2831 1451 38 Below 20 MeV the evaluation is based completely on the ENDF/B- 2831 1451 39 VI.5(Rev1,Release 2) evaluation by Larson, C. Perey, Hetrich, and 2831 1451 40 Fu. 2831 1451 41 2831 1451 42 INCIDENT NEUTRON ENERGIES > 20 MeV 2831 1451 43 2831 1451 44 The ENDF/B-VI Release 2 evaluation extends to 20 MeV and 2831 1451 45 includes cross sections and energy-angle data for all 2831 1451 46 significant reactions. The present evaluation utilizes a more 2831 1451 47 compact composite reaction spectrum representation above 20 MeV 2831 1451 48 in order to reduce the length of the file. No essential data for 2831 1451 49 applications is lost with this representation. 2831 1451 50 The evaluation above 20 MeV utilizes MF=6, MT=5 to represent 2831 1451 51 all reaction data. Production cross sections and emission 2831 1451 52 spectra are given for neutrons, protons, deuterons, tritons, 2831 1451 53 alpha particles, gamma rays, and all residual nuclides produced 2831 1451 54 (A>5) in the reaction chains. To summarize, the ENDF sections 2831 1451 55 with non-zero data above En = 20 MeV are: 2831 1451 56 2831 1451 57 MF=3 MT= 1 Total Cross Section 2831 1451 58 MT= 2 Elastic Scattering Cross Section 2831 1451 59 MT= 3 Nonelastic Cross Section 2831 1451 60 MT= 5 Sum of Binary (n,n') and (n,x) Reactions 2831 1451 61 2831 1451 62 MF=4 MT= 2 Elastic Angular Distributions 2831 1451 63 2831 1451 64 MF=6 MT= 5 Production Cross Sections and Energy-Angle 2831 1451 65 Distributions for Emission Neutrons, Protons, 2831 1451 66 Deuterons, Tritons, and Alphas; and Angle- 2831 1451 67 Integrated Spectra for Gamma Rays and Residual 2831 1451 68 Nuclei That Are Stable Against Particle Emission 2831 1451 69 2831 1451 70 The evaluation is based on nuclear model calculations that 2831 1451 71 have been benchmarked to experimental data, especially for n + 2831 1451 72 Ni58 and p + Ni58 reactions [Ch97]. We use the GNASH code system 2831 1451 73 [Yo92], which utilizes Hauser-Feshbach statistical, 2831 1451 74 preequilibrium and direct-reaction theories. Spherical optical 2831 1451 75 model calculations are used to obtain particle transmission 2831 1451 76 coefficients for the Hauser-Feshbach calculations, as well as 2831 1451 77 for the elastic neutron angular distributions. 2831 1451 78 Cross sections and spectra for producing individual residual 2831 1451 79 nuclei are included for reactions. The energy-angle-correlations 2831 1451 80 for all outgoing particles are based on Kalbach systematics 2831 1451 81 [Ka88]. 2831 1451 82 A model was developed to calculate the energy distributions of 2831 1451 83 all recoil nuclei in the GNASH calculations [Ch96]. The recoil 2831 1451 84 energy distributions are represented in the laboratory system in 2831 1451 85 MT=5, MF=6, and are given as isotropic in the lab system. All 2831 1451 86 other data in MT=5,MF=6 are given in the center-of-mass system. 2831 1451 87 This method of representation utilizes the LCT=3 option approved 2831 1451 88 at the November, 1996, CSEWG meeting. 2831 1451 89 Preequilibrium corrections were performed in the course of the 2831 1451 90 GNASH calculations using the exciton model of Kalbach [Ka77, 2831 1451 91 Ka85], validated by comparison with calculations using Feshbach, 2831 1451 92 Kerman, Koonin (FKK) theory [Ch93]. Discrete level data from 2831 1451 93 nuclear data sheets were matched to continuum level densities 2831 1451 94 using the formulation of Gilbert and Cameron [Gi65] and pairing 2831 1451 95 and shell parameters from the Cook [Co67] analysis. Neutron and 2831 1451 96 charged- particle transmission coefficients were obtained from 2831 1451 97 the optical potentials, as discussed below. Gamma-ray 2831 1451 98 transmission coefficients were calculated using the Kopecky-Uhl 2831 1451 99 model [Ko90]. 2831 1451 100 2831 1451 101 SOME Ni-SPECIFIC INFORMATION CONCERNING THE EVAL. 2831 1451 102 2831 1451 103 The neutron total cross section was evaluated based on the 2831 1451 104 least-squares method taking account of the experimental 2831 1451 105 data [Du67, Bo71, St71, Sm79, Fe80, Pe82, Ha82a, Di97]. The data 2831 1451 106 for natural Ni [Di97] was also used because there was not enough 2831 1451 107 data for Ni-60 above 20 MeV. The data for natural Ni were 2831 1451 108 transformed to the Ni-60 cross section according to A*(2/3) law. 2831 1451 109 Result of this estimation was used as the evaluated total cross 2831 1451 110 section data above 20 MeV. 2831 1451 111 2831 1451 112 The evaluated total cross section data (1 to 250 MeV), s-wave 2831 1451 113 strength function [Mu81] and elastic scattering angular 2831 1451 114 distribution data [Bo71, Gu85, Tu73, Ya79] were used to obtain the2831 1451 115 neutron optical potential parameters. The parameter estimation was2831 1451 116 carried out based on Marquart-Bayesian approach [Sm91], where 2831 1451 117 ECIS95 code [Ra96] was used for the optical model calculation. We2831 1451 118 have employed the energy dependence of the optical potential 2831 1451 119 similar to Delaroche's work [De89]. The initial potential 2831 1451 120 parameters were adopted from Koning and Delaroche [Ko97]. A total2831 1451 121 of 7 parameters concerning the central potential depth were 2831 1451 122 estimated with associated covariance matrix, while the geometrical2831 1451 123 parameters were fixed to the result of a similar search for n + 2831 1451 124 Ni-58. Presently obtained potential was used for the calculation 2831 1451 125 of neutron transmission coefficients and DWBA cross sections in 2831 1451 126 the energy region above 20 MeV. Below 20 MeV, the Harper neutron 2831 1451 127 potential [Ha82b] was used for the calculation of transmission 2831 1451 128 coefficients. 2831 1451 129 2831 1451 130 The proton optical potential was also searched to obtain a good 2831 1451 131 description of proton-total reaction cross section as predicted by2831 1451 132 Wellisch-Axen systematic [We96] above 50 MeV. The parameter 2831 1451 133 estimation was carried out by the Marquart-Bayesian approach 2831 1451 134 similar to the neutron OMP, but trying to seek the best parameter 2831 1451 135 to reproduce the reaction cross sections compiled by Carlson 2831 1451 136 [Ca96] and Wellisch values. The experimental data in Carlson 2831 1451 137 [Ca96] was scaled for Ni-60 according to A**(2/3) law. In this 2831 1451 138 search, the geometrical parameters were fixed to be same as the 2831 1451 139 neutron potential. The present potential gives a good description2831 1451 140 of the proton total reaction cross section from 10 MeV to 250 MeV.2831 1451 141 However, after some trial and error to reproduce both the elastic 2831 1451 142 scattering and reaction cross section data for Ni-58, we have 2831 1451 143 employed the following combination of proton potentials: 2831 1451 144 2831 1451 145 0 to 5 MeV : Harper potential [Ha82b] 2831 1451 146 6 to 47 MeV : Koning and Delaroche [Ko97] 2831 1451 147 48 to 260 MeV : Present OMP 2831 1451 148 2831 1451 149 For deuterons, the Lohr-Haeberli [Lo74] global potential was used;2831 1451 150 for alpha particles the McFadden-Satchler [Mc66] potential was 2831 1451 151 used; and for tritons the Becchetti-Greenlees [Be71] potential was2831 1451 152 used. The He-3 channel was ignored. 2831 1451 153 2831 1451 154 The direct collective inelastic scattering to the following level 2831 1451 155 in Ni-60 was considered by the DWBA-mode calculation of ECIS95 2831 1451 156 [Ra96]: 2831 1451 157 2831 1451 158 Jpi Ex(MeV) Deformation length 2831 1451 159 2+ 1.331 0.8535 2831 1451 160 2831 1451 161 The deformation length was determined to much the ENDF/B-VI value 2831 1451 162 at 20 MeV. 2831 1451 163 2831 1451 164 Certain nuclear level densities were modified from the default 2831 1451 165 values in accordance with experimental level-density information 2831 1451 166 as follows. The level density of 57Fe was matched to the observed 2831 1451 167 D-0 value by modifying the pairing energy to 0.15 MeV; the level 2831 1451 168 density of the main competition channel, neutron emission to 60Ni,2831 1451 169 was adjusted to match Fischer et al.'s [Fi86] value of 3.85e3+-25%2831 1451 170 at 11 MeV excitation energy, but then increased slightly (a total 2831 1451 171 density increase of 11%) by using a pairing energy of 1.1 MeV, 2831 1451 172 since Haight's alpha production at 14 MeV is approx. 11% smaller 2831 1451 173 than Fischer et al.'s measurements. Production of residual nuclei 2831 1451 174 59Ni and 56Fe, through (n,2n) and (n,na) reactions, become 2831 1451 175 particularly important above 14 MeV. Pairing energies were 2831 1451 176 adjusted to match the level density for 59Ni at the neutron 2831 1451 177 binding energy (D0=12.9 keV), and Fischer et al.'s result for the 2831 1451 178 56Fe level density at 11 MeV. 2831 1451 179 2831 1451 180 The new Haight et al. [Ha97] LANL/WNR 60Ni(n,x alpha) data up to 2831 1451 181 50 MeV was used to benchmark our model calculations [Ch97] - 2831 1451 182 agreement with experiment was good. 2831 1451 183 2831 1451 184 **************************************************************** 2831 1451 185 2831 1451 186 REFERENCES 2831 1451 187 2831 1451 188 [Be71] F.D. Becchetti, Jr., and G.W. Greenlees in 2831 1451 189 "Polarization Phenomena in Nuclear Reactions," (Ed: H.H. 2831 1451 190 Barschall and W. Haeberli, The University of Wisconsin Press, 2831 1451 191 1971) p.682 2831 1451 192 [Bo71] P. Boschung et al, Nucl.Phys. A161, 593 (1971) 2831 1451 193 [Ca96] R.F. Carlson, Atomic Data and Nuclear Data Tables, 63, 2831 1451 194 93 (1996) 2831 1451 195 [Ch93] M.B. Chadwick and P.G. Young, Phys.Rev. C 47, 2255 (1993) 2831 1451 196 [Ch96] M.B. Chadwick, P.G. Young, R.E. MacFarlane, and A.J. 2831 1451 197 Koning, "High-Energy Nuclear Data Libraries for Accelerator- 2831 1451 198 Driven Technologies: Calculational Method for Heavy Recoils," 2831 1451 199 Proc. of 2nd Int. Conf. on Accelerator Driven Transmutation 2831 1451 200 Technology and Applications, Kalmar, Sweden, 3-7 June 1996 2831 1451 201 [Ch97] M.B. Chadwick and P.G. Young, "Model Calculations of 2831 1451 202 n,p + 58,60,61,62,64Ni" in APT PROGRESS REPORT: 1 August - 1 2831 1451 203 September 1997, internal Los Alamos National Laboratory memo T-2831 1451 204 2-97/MS-51, 8 September 1997 from R.E. MacFarlane to L. Waters.2831 1451 205 [Ch99] M.B. Chadwick, P.G. Young, G.M. Hale, et al., Los Alamos 2831 1451 206 National Laboratory report, LA-UR-99-1222 (1999) 2831 1451 207 [Ci68] S. Cierjack et al, report KFK-1000 (1968) 2831 1451 208 [Co67] J.L. Cook, H. Ferguson, and A.R. DeL Musgrove, Aust.J. 2831 1451 209 Phys. 20, 477 (1967) 2831 1451 210 [De89] J.P. Delaroche, Y. Wang and J. Rapaport, Phys.Rev.C 39, 2831 1451 211 391 (1989) 2831 1451 212 [Di97] F. Dietrich et al., private communication (1997). 2831 1451 213 [Du67] Yu.V. Dukarevich et al., Nucl.Phys. A92, 433 (1967) 2831 1451 214 [Fe80] M.B. Fedorov et al., 80Kiev, 1, 309(1980) 2831 1451 215 [Fi86] R. Fischer, G. Traxler, M. Uhl at al., Phys Rev C34, 460 2831 1451 216 (1986) 2831 1451 217 [Fr01] S.C. Frankle, R.C. Reedy, and P.G. Young, Los ALamos 2831 1451 218 National Laboratory Report, LA-13812 (2001). 2831 1451 219 [Fu96] C.Y. Fu, "Effects of shape differences in the level 2831 1451 220 densities of three formalisms on calculated cross sections", 2831 1451 221 personal communication, 1996 (to be published by the IAEA). 2831 1451 222 [Gi65] A. Gilbert and A.G.W. Cameron, Can.J.Phys. 43, 1446 (1965)2831 1451 223 [Gu85] P.P. Guss et al, Nucl.Phys. A438, 187 (1985) 2831 1451 224 [Ha82a] J.A. Harvey et al, 82Anterp (1982) p. 856 2831 1451 225 [Ha82b] R.C. Harper and W.L. Alford, J.Phys.G. 8, 153 (1982) 2831 1451 226 [Ha97] R.C. Haight, F.B. Bateman, S.M. Sterbenz et al., Nuclear 2831 1451 227 Data for Science and Technol., Proc. Conf. Trieste, Italy, May 2831 1451 228 1997, Vol. I (Edit. Compositori, Bologna, Italy, 1997) p. 603 2831 1451 229 [Ka77] C. Kalbach, Z.Phys.A 283, 401 (1977) 2831 1451 230 [Ka85] C. Kalbach, Los Alamos National Laboratory report 2831 1451 231 LA-10248-MS (1985) 2831 1451 232 [Ka88] C. Kalbach, Phys.Rev.C 37, 2350 (1988); see also 2831 1451 233 C. Kalbach and F. M. Mann, Phys.Rev.C 23, 112 (1981) 2831 1451 234 [Ko90] J. Kopecky and M. Uhl, Phys.Rev.C 41, 1941 (1990) 2831 1451 235 [Ko97] A. Koning and J.P. Delaroche, private communication. 2831 1451 236 [La83] D.C. Larson et al, report ORNL-TM-8203 (1983) 2831 1451 237 [Lo74] J.M.Lohr and W.Haeberli, Nucl.Phys. A232, 381 (1974) 2831 1451 238 [Mc66] L. McFadden and G.R. Satchler, Nucl.Phys. 84, 177 (1966) 2831 1451 239 [Mu81] S.F. Mughabghab, M. Divadeenam and N.E. Holden, "Neutron 2831 1451 240 Cross Sections", Vol. 1, Part A (Academic Press, 1981) 2831 1451 241 [Pe73] F.G. Perey, private communication (1973) [EXFOR 10342] 2831 1451 242 [Pe82] C.M. Perey et al, report ORNL-5893 (1982) 2831 1451 243 [Pe88] Pedroni et al, Phys.Rev.C 38, 2052 (1988) 2831 1451 244 [Po81] W. Poenitz, Proc. Conf. on Nuclear Data Evaluation Methods2831 1451 245 and Procedures, Brookhaven National Laboratory Report BNL-NCS- 2831 1451 246 51363, p.249(1981). 2831 1451 247 [Ra96] J. Raynal, "Notes on ECIS94", Service de Physique 2831 1451 248 Theorique, Saclay, France (personal communication through A. J.2831 1451 249 Koning, 1996). 2831 1451 250 [Sc73] W. Schimmerling et al., Phys.Rev.C 7, 248 (1973) 2831 1451 251 [Sm79] A.B. Smith et al., Nucl.Sci.Eng., 72, 293 (1979) 2831 1451 252 [Sm91] D.L. Smith, "Probability, Statistics, and Data Uncertainty2831 1451 253 in Nuclear Science and Technology" (American Nuclear Society, 2831 1451 254 1991) 2831 1451 255 [Sm92] A.B. Smith et al., J.Phys.G, 18, 629 (1992) 2831 1451 256 [St71] P. Stoler et al,, 71Knox, 1, 311 (1971) 2831 1451 257 [Tu73] A.I. Tutubalin et al., Neutron Physics, Proc. Conf., Kiev,2831 1451 258 Ukraine, 1973, Vol. 3 [EXFOR 40417] p. 62 2831 1451 259 [Ul83] J.J. Ullmann, F.P. Brady, C.M. Castaneda, et al., Nucl. 2831 1451 260 Phys. A427, 493 (1984) 2831 1451 261 [We96] H.P. Wellisch and D. Axen, Phys.Rev.C 54, 1329 (1996) 2831 1451 262 [Ya79] Y. Yamanouti, J. Rapaport, S.M. Grimes et al, Nuclear 2831 1451 263 Cross Sections for Technology, Proc. Conf., Knoxville, TN, 2831 1451 264 1979, NBS Special Publication 594 (1980) [EXFOR 10953] 2831 1451 265 [Yo92] P.G. Young, E.D. Arthur, and M.B. Chadwick, Los Alamos 2831 1451 266 report LA-12343-MS (1992) 2831 1451 267 2831 1451 268 **************************************************************** 2831 1451 269 2831 1451 270 ENDF/B-VI MOD 2 Revision, July 1991, D.C. Larson, C.M. Perey, 2831 1451 271 D.M. Hetrick, and C.Y. Fu (ORNL) 2831 1451 272 2831 1451 273 REVISION 1 CHANGES 2831 1451 274 The resonance region from 1.E-5 eV to 450 keV has been changed,2831 1451 275 based on a SAMMY analysis by F. G. Perey of new 60Ni ORELA data 2831 1451 276 up to 100 keV of Harvey, Hill and Perey. This new work reproduces2831 1451 277 the thermal cross sections and includes the small resonances 2831 1451 278 inadvertently left out in the original file. No background 2831 1451 279 cross sections are required in file 3 in the resonance region. 2831 1451 280 Removed elastic transformation matrix. 2831 1451 281 2831 1451 282 **************************************************************** 2831 1451 283 2831 1451 284 ENDF/B-VI MOD 1 Evaluation, October 1989, D.C. Larson, 2831 1451 285 C.M. Perey, D.M. Hetrick, and C.Y. Fu (ORNL) 2831 1451 286 2831 1451 287 This work employed nuclear model codes including the 2831 1451 288 Distorted Wave Born Approximation (DWBA) program DWUCK (1) 2831 1451 289 and the Hauser-Feshbach code TNG (2,3,4). The TNG code provides 2831 1451 290 energy and angular distributions of particles emitted in the 2831 1451 291 compound and pre-compound reactions, ensures consistency among 2831 1451 292 all reactions, and maintains energy balance. Details pertinent 2831 1451 293 to the contents of this evaluation and extensive comparisons of 2831 1451 294 calculations with experimental data can be found in Hetrick (5). 2831 1451 295 2831 1451 296 ----- DESCRIPTION OF FILES 2831 1451 297 (MF-MT) 2831 1451 298 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2831 1451 299 2-151 RESONANCE PARAMETERS -- TAKEN FROM REF (6). THE NEGATIVE 2831 1451 300 ENERGY RESONANCES WERE ADJUSTED BY THE AUTHOR, C. M. PEREY2831 1451 301 TO GIVE THE PROPER THERMAL SCATTERING AND CAPTURE. USING 2831 1451 302 THESE MODIFIED RESULTS, NO BACKGROUND IS REQUIRED IN 3/1 2831 1451 303 IE, THE TOTAL, SCATTERING AND CAPTURE IS GIVEN COMPLETELY 2831 1451 304 BY THE RESONANCE PARAMETERS FROM 1.E-5 EV TO 450 KEV. 2831 1451 305 RESONANCE PARAMETERS ARE FROM A REICH-MOORE ANALYSIS WITH 2831 1451 306 THE CODE SAMMY (REF 7). 2831 1451 307 THUS, THE THERMAL CROSS SECTIONS ARE GIVEN BY THE 2831 1451 308 RESONANCE PARAMETERS AND HAVE VALUES: TOTAL 3.9 B, 2831 1451 309 ELASTIC SCATTERING 0.98 B, AND CAPTURE 2.92 B. 2831 1451 310 NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2831 1451 311 OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE 2831 1451 312 PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON 2831 1451 313 A FINER ENERGY GRID THAN GIVEN IN 4/2. 2831 1451 314 3-1 TOTAL CROSS SECTION -- FROM 450 KEV TO 1611 KEV THE DATA 2831 1451 315 OF REF (8) WERE USED. FROM 1611 KEV TO 20 MEV THE DATA 2831 1451 316 OF REF (9) WERE USED. SEVERAL LOWER RESOLUTION DATA SETS 2831 1451 317 WERE ENERGY-BINNED AND CHECKED WITH BINNED DATA FROM 8,9. 2831 1451 318 3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY 2831 1451 319 SUBTRACTING THE NONELASTIC FROM THE TOTAL 2831 1451 320 3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22, 2831 1451 321 3-28, 3-102, 3-103, 3-104, AND 3-107. 2831 1451 322 3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, .. 2831 1451 323 .., 3-61, AND 3-91 2831 1451 324 3-16 (N,2N) CROSS SECTIONS WERE CALCULATED BY THE TNG 2831 1451 325 CODE (2,3,4,5), NO 60NI DATA AVAILABLE. 2831 1451 326 3-22 (N,NA) CROSS SECTIONS WERE CALCULATED BY THE TNG 2831 1451 327 CODE (2,3,4,5). NO 60NI DATA AVAILABLE OTHER THAN A EMISS 2831 1451 328 3-28 (N,NP) CROSS SECTIONS WERE CALCULATED BY THE TNG 2831 1451 329 CODE (2,3,4,5). NO 60NI DATA AVAILABLE OTHER THAN P EMISS 2831 1451 330 3-51 TO 3-61 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE 2831 1451 331 FROM TNG (2,3,4,5) WHICH INCLUDES DIRECT INTERACTION 2831 1451 332 CROSS SECTIONS FROM DWUCK (1) CALCULATIONS. CALCULATIONS 2831 1451 333 COMPARED WITH EXTENSIVE EXPERIMENTAL DATA (5). 3-51 CROSS2831 1451 334 SECTIONS ABOVE 4.0 MEV ADJUSTED TO BETTER FIT RECENT 2831 1451 335 MEASURED DATA. 2831 1451 336 3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM (TNG 2831 1451 337 CALCULATED). 2831 1451 338 3-102 (N,G) CAPTURE CROSS SECTION TAKEN FROM RESONANCE PARAMETER2831 1451 339 FROM 1.E-5 EV TO 450 KEV. TNG CALCULATIONS WERE 2831 1451 340 NORMALIZED TO THE AVERAGED CROSS SECTION OBTAINED FROM THE2831 1451 341 RESONANCE PARAMETERS FROM 100-450 KEV. THESE NORMALIZED 2831 1451 342 TNG RESULTS WERE USED FROM 450 KEV TO 20 MEV. 2831 1451 343 3-103 (N,P) CROSS SECTIONS FOR EN LESS THAN OR EQUAL TO 12 MEV 2831 1451 344 WERE TAKEN FROM A CURVE DRAWN THROUGH THE DATA OF VONACH 2831 1451 345 ET AL. (10). THIS CURVE WAS CONNECTED TO THE ANL DATA OF 2831 1451 346 GREENWOOD (11) FROM 14.5 TO 15.0 MEV. FROM 15.0 TO 20.0 2831 1451 347 MEV THE DATA OF PAULSEN AND LISKIEN (12) WERE USED 2831 1451 348 AS A GUIDE. THE NEW DATA BY VONACH ET AL. (10) 2831 1451 349 RESULT IN AN INTEGRAL VALUE CLOSE TO THE 2.39 VALUE OF 2831 1451 350 MANNHART (13). 2831 1451 351 3-104 (N,D) CROSS SECTION - ENDF/B-V (14) VALUES WERE NORMALIZED2831 1451 352 TO THE DATA OF GRIMES ET AL. (15). 2831 1451 353 3-107 (N,A) CROSS SECTIONS WERE CALCULATED BY THE 2831 1451 354 TNG CODE (2,3,4,5). LIMITED DATA OTHER THAN A EMISSION. 2831 1451 355 4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR 2831 1451 356 ELASTIC SCATTERING ARE FROM ENDF/B-V. AGREE WELL WITH DATA2831 1451 357 IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY 2831 1451 358 THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE 2831 1451 359 PARAMETERS IN 2/151. 2831 1451 360 6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2831 1451 361 NEUTRON AND 59NI RESIDUAL, AND ENERGY DEPENDENT YIELD 2831 1451 362 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2831 1451 363 RAY; TNG CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR2831 1451 364 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2831 1451 365 THE OUTGOING NEUTRON). COMPARES WELL WITH N EMISSION DATA2831 1451 366 WHEN COMBINED WITH N FROM 6/22, 6/28 AND 6/91. 2831 1451 367 6-22 (N,NA)+(N,AN); INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2831 1451 368 NEUTRON, ALPHA, AND 56FE RESIDUAL, AND ENERGY DEPENDENT 2831 1451 369 YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE 2831 1451 370 GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2831 1451 371 FOR EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY 2831 1451 372 FOR THE OUTGOING NEUTRON; ISOTROPY IS ASSUMED FOR THE 2831 1451 373 ALPHA AND RESIDUAL). 2831 1451 374 6-28 (N,NP)+(N,PN); INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2831 1451 375 NEUTRON, P, AND 59CO RESIDUAL, AND ENERGY DEPENDENT YIELD 2831 1451 376 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2831 1451 377 RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR 2831 1451 378 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2831 1451 379 THE OUTGOING NEUTRON). 2831 1451 380 6-51 THROUGH 6-61 INELASTIC SCATTERING EXCITING LEVELS; EACH 2831 1451 381 SECTION INCLUDES SIMPLE CONSTANT YIELDS FOR THE NEUTRON 2831 1451 382 AND 60NI RESIDUAL; ANGULAR DISTRIBUTIONS ARE GIVEN FOR 2831 1451 383 THE OUTGOING NEUTRON (LEGENDRE COEFFICIENTS COMPUTED 2831 1451 384 BY DWUCK (1) AND TNG (2,3,4,5)), COMPARED WITH DATA IN (5)2831 1451 385 6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES 2831 1451 386 SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 60NI 2831 1451 387 RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG 2831 1451 388 CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; TNG 2831 1451 389 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2831 1451 390 FOR EACH (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR THE 2831 1451 391 OUTGOING NEUTRON). 2831 1451 392 6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P 2831 1451 393 AND 60CO RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2831 1451 394 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2831 1451 395 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2831 1451 396 PRODUCT. COMPARES WELL WITH P EMISSION DATA WHEN COMBINED2831 1451 397 WITH 6/28. 2831 1451 398 6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A 2831 1451 399 AND 57FE RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2831 1451 400 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2831 1451 401 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2831 1451 402 PRODUCT. COMPARES WELL WITH A EMISSION DATA WHEN COMBINED2831 1451 403 WITH 6/22. 2831 1451 404 12-51 THROUGH 12-61 BRANCHING RATIOS FOR THE LEVELS, COMPILED 2831 1451 405 BY HETRICK ET AL. (5), ARE GIVEN. 2831 1451 406 12-102 (N,G) CAPTURE; MULTIPLICITIES WERE TNG CALCULATED. 2831 1451 407 14-51 THROUGH 14-58 AND 14-102 GAMMA RAY ANGULAR DISTRIBUTIONS 2831 1451 408 ASSUMED TO BE ISOTROPIC. 2831 1451 409 15-102 (N,G) CAPTURE; TNG CALCULATED 2831 1451 410 2831 1451 411 -------------------------------------------------------------- 2831 1451 412 UNCERTAINTY FILES 2831 1451 413 AN LB=8 SECTION IS INCLUDED FOR ALL NON-DERIVED FILES AS 2831 1451 414 REQUIRED BY ENDF/B-VI. 2831 1451 415 2831 1451 416 33-1 UNCERTAINTIES ARE DERIVED FROM 1.E-5 TO 100 EV. FROM 100 2831 1451 417 EV TO 20 MEV THEY ARE EXPLICIT, USING LB=0,1 AND 8. 2831 1451 418 33-2 FROM 1.E-5 TO 100 EV, UNCERTAINTIES ARE EXPLICIT, BASED 2831 1451 419 UPON THERMAL UNCERTAINTY AND OTHER DATA. FROM 100 EV TO 2831 1451 420 20 MEV THE FILES ARE DERIVED. 2831 1451 421 33-3 FROM 1.E-5 TO 450 KEV UNCERTAINTIES ARE DERIVED. FROM 4502831 1451 422 KEV TO 20 MEV UNCERTAINTIES ARE EXPLICIT, USING LB=1 AND 82831 1451 423 33-4 UNCERTAINTIES ARE ALL DERIVED. 2831 1451 424 33-16 COVARIANCES WERE ESTIMATED AS NO DATA AVAILABLE. 2831 1451 425 33-22 UNCERTAINTIES FOR (N,NA) ARE EXPLICIT, ESTIMATED FROM TNG 2831 1451 426 33-28 UNCERTAINTIES FOR (N,NP) ARE EXPLICIT, ESTIMATED FROM DATA2831 1451 427 AND CALCULATION. 2831 1451 428 33-51-91 UNCERTAINTIES FOR INELASTIC SCATTERING ARE EXPLICIT, 2831 1451 429 BASED ON DATA AND CALCULATION UNCERTAINTIES. 2831 1451 430 33-102 UNCERTAINTIES ARE EXPLICIT, BASED ON THERMAL DATA AT LOW 2831 1451 431 ENERGIES, AND CALCULATED RESULTS ABOVE 450 KEV. 2831 1451 432 33-103 COVARIANCES - DATA OF VONACH ET AL. (10) AND CSISRS DATA 2831 1451 433 USED AS A GUIDE. 2831 1451 434 33-104 UNCERTAINTIES ESTIMATED, BASED ON DATA 2831 1451 435 33-107 UNCERTAINTIES EXPLICIT, BASED ON DATA AND TNG RESULTS. 2831 1451 436 ---------------------------------------------------------------- 2831 1451 437 REFERENCES: 2831 1451 438 (1) P.D. Kunz, "DISTORTED WAVE CODE DWUCK72," UNIV. OF 2831 1451 439 COLORADO, UNPUBLISHED (1972). 2831 1451 440 (2) C.Y. Fu, Oak Ridge report ORNL/TM-7042 (1980) 2831 1451 441 (3) C.Y Fu, Neutron Cross Sections from 10 to 50 MeV, Proc. Symp.2831 1451 442 Upton, NY, May 1980, Brookhaven report BNL-NCS-51425 (1980) 2831 1451 443 p. 675 2831 1451 444 (4) K. Shibata and C.Y. Fu, Oak Ridge National Laboratory report 2831 1451 445 ORNL/TM-10093 (1986) 2831 1451 446 (5) D.M. Hetrick, C.Y. Fu, and D.C. Larson, Oak Ridge National 2831 1451 447 Laboratory report ORNL/TM-10219 [ENDF-344] (1987) 2831 1451 448 (6) C.M. Perey, J.A. Harvey, R.L. Macklin, et al., Phys.Rev.C, 2831 1451 449 27, 2556 (1983) 2831 1451 450 (7) N.M. Larson and F.G. Perey, Oak Ridge National Laboratory 2831 1451 451 reports ORNL/TM-7485 (1980); ORNL/TM-9179 (1984); 2831 1451 452 ORNL/TM-9179/R1 (1985); ORNL/TM-9179/R2 (1988) 2831 1451 453 (8) J.A. Harvey, ORELA, 80-M NE110 TA TARGET DATA, SENT TO NNDC 2831 1451 454 (9) J.A. Harvey, ORELA, 80-M NE110 BE BLOCK DATA, SENT TO NNDC 2831 1451 455 (10) H. Vonach, M. Wagner, and R.C. Haight, "Neutron cross 2831 1451 456 sections of 58Ni and 60Ni for 8-12 MeV neutrons," private 2831 1451 457 communication, 1989 2831 1451 458 (11) L.R. Greenwood, report DOE-ER-0046-21 (1985) p. 15 2831 1451 459 (12) A. Paulsen, Nukleonik 10, 91 (1967) 2831 1451 460 (13) W. Mannhart, Proc. Fourth ASTM-Euratom Symp. on Reactor 2831 1451 461 Dosimetry, Vol. II, March 22-26, 1982 (1982) p. 637 2831 1451 462 (14) M. Divadeenam, Brookhaven National Laboratory report 2831 1451 463 BNL-NCS-51346 [ENDF-294] (1979) 2831 1451 464 (15) S.M. Grimes, R.C. Haight, K.R. Alvar, et al., Phys.Rev.C 2831 1451 465 19, 2127 (1979) 2831 1451 466 2831 1451 467 ************************ C O N T E N T S *********************** 2831 1451 468 ***************** Program LINEAR (VERSION 2004-1) ***************2831 1451 469 For All Data Greater than 1.0000E-10 barns in Absolute Value 2831 1451 470 Data Linearized to Within an Accuracy of .100000000 per-cent 2831 1451 471 ***************** Program RECENT (VERSION 2004-1) ***************2831 1451 472 for All Data Greater than 1.0000E-10 barns in Absolute Value 2831 1451 473 Data Linearized to within an Accuracy of .100000000 per-cent 2831 1451 474 ***************** Program FIXUP (Version 2004-1) ****************2831 1451 475 Corrected ZA/AWR in All Sections-----------------------------Yes 2831 1451 476 Corrected Thresholds-----------------------------------------No 2831 1451 477 Extended Cross Sections to 20 MeV----------------------------No 2831 1451 478 Allow Cross Section Deletion---------------------------------No 2831 1451 479 Allow Cross Section Reconstruction---------------------------Yes 2831 1451 480 Make All Cross Sections Non-Negative-------------------------Yes 2831 1451 481 Delete Energies Not in Ascending Order-----------------------Yes 2831 1451 482 Deleted Duplicate Points-------------------------------------Yes 2831 1451 483 Check for Ascending MAT/MF/MT Order--------------------------Yes 2831 1451 484 Check for Legal MF/MT Numbers--------------------------------Yes 2831 1451 485 Allow Creation of Missing Sections---------------------------No 2831 1451 486 Allow Insertion of Energy Points-----------------------------No 2831 1451 487 Create Uniform Energy Grid-----------------------------------No 2831 1451 488 Delete Section if Cross Section =0 at All Energies-----------Yes 2831 1451 489 **************** Program DICTIN (VERSION 2004-1) ****************2831 1451 490 1 451 583 42831 1451 491 2 151 279 22831 1451 492 3 1 30450 32831 1451 493 3 2 30428 32831 1451 494 3 3 29951 32831 1451 495 3 4 17 12831 1451 496 3 5 9 32831 1451 497 3 16 6 12831 1451 498 3 22 7 12831 1451 499 3 28 7 12831 1451 500 3 51 14 12831 1451 501 3 52 13 12831 1451 502 3 53 12 12831 1451 503 3 54 12 12831 1451 504 3 55 12 12831 1451 505 3 56 11 12831 1451 506 3 57 11 12831 1451 507 3 58 11 12831 1451 508 3 59 11 12831 1451 509 3 60 11 12831 1451 510 3 61 11 12831 1451 511 3 91 11 12831 1451 512 3 102 29931 42831 1451 513 3 103 12 12831 1451 514 3 104 12 12831 1451 515 3 107 13 12831 1451 516 4 2 3747 32831 1451 517 6 5 13370 32831 1451 518 6 16 316 12831 1451 519 6 22 421 12831 1451 520 6 28 413 12831 1451 521 6 51 47 12831 1451 522 6 52 44 12831 1451 523 6 53 7 12831 1451 524 6 54 41 12831 1451 525 6 55 7 12831 1451 526 6 56 41 12831 1451 527 6 57 7 12831 1451 528 6 58 7 12831 1451 529 6 59 7 12831 1451 530 6 60 7 12831 1451 531 6 61 7 12831 1451 532 6 91 1295 12831 1451 533 6 103 819 12831 1451 534 6 107 847 12831 1451 535 12 51 3 12831 1451 536 12 52 3 12831 1451 537 12 53 3 12831 1451 538 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