28-Ni- 58 ENDF/B-VI, Processed by Red Cullen using PREPRO2004 6000 0 0 0 2.80580E+4 5.74380E+1 2 0 0 42825 1451 1 0.0 0.0 0 0 0 62825 1451 2 1.00000E+0 1.50000E+8 8 0 10 62825 1451 3 0.0 0.0 1 0 549 782825 1451 4 28-Ni- 58 LANL,ORNL EVAL-SEP97 S.CHIBA,M.B.CHADWICK,LARSON 2825 1451 5 Ch97,Ch99 DIST-SEP 1 REV3- 20010926 2825 1451 6 ----ENDF/B-VI MATERIAL 2825 REVISION 2 2825 1451 7 -----INCIDENT NEUTRON DATA 2825 1451 8 ------ENDF-6 FORMAT 2825 1451 9 2825 1451 10 **************************************************************** 2825 1451 11 2825 1451 12 ENDF/B-VI MOD 4 Revision, June 2000, S.C. Frankle, R.C. Reedy, 2825 1451 13 P.G. Young (LANL) 2825 1451 14 2825 1451 15 The secondary gamma-ray spectrum for radiative capture (MF 12, 2825 1451 16 MT 102) has been updated for new experimental data at incident 2825 1451 17 neutron energies up to 1 keV. 2825 1451 18 The MF=12, MT=102 yields above 1 keV were adjusted slightly to 2825 1451 19 force energy conservation. 2825 1451 20 The Q-value for radiative capture was also updated in File 3. 2825 1451 21 Details of these changes are described in Frankel et al. [Fr01]. 2825 1451 22 2825 1451 23 **************************************************************** 2825 1451 24 2825 1451 25 ENDF/B-VI MOD 3 Evaluation, September 1997, S. Chiba, 2825 1451 26 M.B. Chadwick, P.G. Young (LANL), and A.J. Koning (ECN) 2825 1451 27 2825 1451 28 Los Alamos LA150 Library, produced with FKK/GNASH/GSCAN code 2825 1451 29 in cooperation with ECN Petten. 2825 1451 30 2825 1451 31 This evaluation provides a complete representation of the 2825 1451 32 nuclear data needed for transport, damage, heating, 2825 1451 33 radioactivity, and shielding applications over the incident 2825 1451 34 neutron energy range from 1.0E-11 to 150 MeV. The discussion 2825 1451 35 here is divided into the region below and above 20 MeV. 2825 1451 36 2825 1451 37 INCIDENT NEUTRON ENERGIES < 20 MeV 2825 1451 38 2825 1451 39 Below 20 MeV the evaluation is based completely on the ENDF/B- 2825 1451 40 VI.5 (Rev1,Release 2) evaluation by Larson, C. Perey, Hetrich, 2825 1451 41 and Fu. 2825 1451 42 2825 1451 43 INCIDENT NEUTRON ENERGIES > 20 MeV 2825 1451 44 2825 1451 45 The ENDF/B-VI Release 2 evaluation extends to 20 MeV and 2825 1451 46 includes cross sections and energy-angle data for all 2825 1451 47 significant reactions. The present evauation utilizes a more 2825 1451 48 compact composite reaction spectrum representation above 20 MeV 2825 1451 49 in order to reduce the length of the file. No essential data for 2825 1451 50 applications is lost with this representation. 2825 1451 51 The evaluation above 20 MeV utilizes MF=6, MT=5 to represent 2825 1451 52 all reaction data. Production cross sections and emission 2825 1451 53 spectra are given for neutrons, protons, deuterons, tritons, 2825 1451 54 alpha particles, gamma rays, and all residual nuclides produced 2825 1451 55 (A>5) in the reaction chains. To summarize, the ENDF sections 2825 1451 56 with non-zero data above En = 20 MeV are: 2825 1451 57 2825 1451 58 MF=3 MT= 1 Total Cross Section 2825 1451 59 MT= 2 Elastic Scattering Cross Section 2825 1451 60 MT= 3 Nonelastic Cross Section 2825 1451 61 MT= 5 Sum of Binary (n,n') and (n,x) Reactions 2825 1451 62 2825 1451 63 MF=4 MT= 2 Elastic Angular Distributions 2825 1451 64 2825 1451 65 MF=6 MT= 5 Production Cross Sections and Energy-Angle 2825 1451 66 Distributions for Emission Neutrons, Protons, 2825 1451 67 Deuterons, Tritons, and Alphas; and Angle- 2825 1451 68 Integrated Spectra for Gamma Rays and Residual 2825 1451 69 Nuclei That Are Stable Against Particle Emission 2825 1451 70 2825 1451 71 The evaluation is based on nuclear model calculations that 2825 1451 72 have been benchmarked to experimental data, especially for n + 2825 1451 73 Ni58 and p + Ni58 reactions [Ch97]. We use the GNASH code system 2825 1451 74 [Yo92], which utilizes Hauser-Feshbach statistical, 2825 1451 75 preequilibrium and direct-reaction theories. Spherical optical 2825 1451 76 model calculations are used to obtain particle transmission 2825 1451 77 coefficients for the Hauser-Feshbach calculations, as well as 2825 1451 78 for the elastic neutron angular distributions. 2825 1451 79 Cross sections and spectra for producing individual residual 2825 1451 80 nuclei are included for reactions. The energy-angle-correlations 2825 1451 81 for all outgoing particles are based on Kalbach systematics 2825 1451 82 [Ka88]. 2825 1451 83 A model was developed to calculate the energy distributions of 2825 1451 84 all recoil nuclei in the GNASH calculations [Ch96]. The recoil 2825 1451 85 energy distributions are represented in the laboratory system in 2825 1451 86 MT=5, MF=6, and are given as isotropic in the lab system. All 2825 1451 87 other data in MT=5,MF=6 are given in the center-of-mass system. 2825 1451 88 This method of representation utilizes the LCT=3 option approved 2825 1451 89 at the November, 1996, CSEWG meeting. 2825 1451 90 Preequilibrium corrections were performed in the course of the 2825 1451 91 GNASH calculations using the exciton model of Kalbach [Ka77, 2825 1451 92 Ka85], validated by comparison with calculations using Feshbach, 2825 1451 93 Kerman, Koonin (FKK) theory [Ch93]. Discrete level data from 2825 1451 94 nuclear data sheets were matched to continuum level densities 2825 1451 95 using the formulation of Gilbert and Cameron [Gi65] and pairing 2825 1451 96 and shell parameters from the Cook [Co67] analysis. Neutron and 2825 1451 97 charged- particle transmission coefficients were obtained from 2825 1451 98 the optical potentials, as discussed below. Gamma-ray 2825 1451 99 transmission coefficients were calculated using the Kopecky-Uhl 2825 1451 100 model [Ko90]. 2825 1451 101 2825 1451 102 SOME Ni-SPECIFIC INFORMATION CONCERNING THE EVAL. 2825 1451 103 2825 1451 104 The neutron total cross section was evaluated based on the 2825 1451 105 least-squares method with GMA code system [Po81] taking account of2825 1451 106 the experimental data [Ci68, Pe73, Sc73, La83, Sm92, Di97]. The 2825 1451 107 data for natural Ni was used above 20 MeV because there was no 2825 1451 108 data for Ni-58 at this energy region. The data for natural Ni were2825 1451 109 transformed to the Ni-58 cross section according to A*(2/3) law. 2825 1451 110 In the GMA analysis, the systematic error was assumed to be 1 % 2825 1451 111 for all the data set. Result of the GMA evaluation was used as 2825 1451 112 the evaluated total cross section data above 20 MeV. 2825 1451 113 2825 1451 114 The evaluated total cross section data (1 to 250 MeV), s-wave 2825 1451 115 strength function[Mu81], and elastic scattering angular 2825 1451 116 distribution data [Sm92, Gu85, Tu73, Pe88, Ya79] were used to 2825 1451 117 obtain the neutron optical potential parameters. The parameter 2825 1451 118 estimation was carried out based on Marquart-Bayesian approach 2825 1451 119 [Sm91], where ECIS95 code [Ra96] was used for the optical model 2825 1451 120 calculation. We have employed the energy dependence of the 2825 1451 121 optical potential similar to Delaroche's work [De89]. The initial 2825 1451 122 potential parameters were adopted from Koning and Delaroche 2825 1451 123 [Ko97]. Total of 17 parameters concerning the central potential 2825 1451 124 were estimated with associated covariance matrix. Presently 2825 1451 125 obtained potential was used for the calculation of neutron 2825 1451 126 transmission coefficients and DWBA cross sections in the entire 2825 1451 127 energy region above 20 MeV. Below 20 MeV, the Harper neutron 2825 1451 128 potential [Ha82] was used. 2825 1451 129 2825 1451 130 The proton optical potential was also searched for to obtain a 2825 1451 131 good description of proton-total reaction cross section as 2825 1451 132 predicted by Wellisch-Axen systematic [We96] above 50 MeV. The 2825 1451 133 parameter estimation was carried out by the Marquart-Bayesian 2825 1451 134 approach similar to the neutron OMP, but trying to seek the best 2825 1451 135 parameter to reproduce the reaction cross sections compiled by 2825 1451 136 Carlson [Ca96] and Wellisch values. In this search, the 2825 1451 137 geometrical parameters were fixed to be same as the neutron 2825 1451 138 potential. The present potential gives a good description of the 2825 1451 139 proton total reaction cross section above 10 MeV to 250 MeV. 2825 1451 140 However, after some trial and error to reproduce both the elastic 2825 1451 141 scattering and reaction cross section data, we have employed the 2825 1451 142 following combination of proton potentials: 2825 1451 143 2825 1451 144 0 to 5 MeV : Harper potential [Ha82] 2825 1451 145 5 to 50 MeV : Koning and Delaroche [Ko97] 2825 1451 146 50 to 260 MeV : Present OMP 2825 1451 147 2825 1451 148 For deuterons, the Lohr-Haeberli [Lo74] global potential was used;2825 1451 149 for alpha particles the McFadden-Satchler potential [Mc66] was 2825 1451 150 used; and for tritons the Beccheti-Greenlees [Be71] potential was 2825 1451 151 used. The He-3 channel was ignored. 2825 1451 152 2825 1451 153 The direct collective inelastic scattering to the following levels2825 1451 154 in Ni-58 was considered by the DWBA-mode calculation of ECIS95 2825 1451 155 [Ra96]: 2825 1451 156 2825 1451 157 Jpi Ex(MeV) Deformation length 2825 1451 158 2+ 1.454 0.900 2825 1451 159 4+ 2.459 0.350 2825 1451 160 2+ 3.038 0.242 2825 1451 161 2+ 3.263 0.306 2825 1451 162 4+ 3.620 0.246 2825 1451 163 2+ 3.898 0.111 2825 1451 164 2+ 4.108 0.063 2825 1451 165 4+ 4.299 0.127 2825 1451 166 4+ 4.405 0.329 2825 1451 167 3- 4.475 0.708 2825 1451 168 4+ 4.757 0.403 2825 1451 169 4+ 5.438 0.151 2825 1451 170 4+ 5.472 0.080 2825 1451 171 2+ 5.749 0.048 2825 1451 172 4+ 5.766 0.086 2825 1451 173 2+ 5.906 0.115 2825 1451 174 3- 6.312 0.128 2825 1451 175 2+ 6.417 0.068 2825 1451 176 4+ 6.460 0.098 2825 1451 177 2+ 6.475 0.065 2825 1451 178 2+ 6.569 0.056 2825 1451 179 2+ 6.752 0.141 2825 1451 180 3- 6.854 0.296 2825 1451 181 2+ 6.983 0.116 2825 1451 182 4+ 7.051 0.090 2825 1451 183 4+ 7.068 0.086 2825 1451 184 3- 7.111 0.079 2825 1451 185 4+ 7.141 0.112 2825 1451 186 3- 7.210 0.323 2825 1451 187 2+ 7.272 0.088 2825 1451 188 3- 7.300 0.063 2825 1451 189 3- 7.420 0.048 2825 1451 190 3- 7.514 0.171 2825 1451 191 2+ 7.580 0.051 2825 1451 192 4+ 7.618 0.083 2825 1451 193 3- 7.858 0.106 2825 1451 194 4+ 7.860 0.097 2825 1451 195 3- 8.134 0.142 2825 1451 196 3- 8.797 0.097 2825 1451 197 3- 8.841 0.112 2825 1451 198 4+ 8.902 0.072 2825 1451 199 3- 9.012 0.056 2825 1451 200 3- 9.304 0.065 2825 1451 201 3- 9.379 0.106 2825 1451 202 4+ 9.436 0.071 2825 1451 203 3- 9.458 0.082 2825 1451 204 4+ 9.588 0.052 2825 1451 205 4+ 9.632 0.080 2825 1451 206 3- 9.672 0.121 2825 1451 207 3- 9.835 0.083 2825 1451 208 3- 9.870 0.076 2825 1451 209 3- 9.929 0.061 2825 1451 210 3- 9.956 0.071 2825 1451 211 2825 1451 212 These data were retrieved from the literature (Nuclear Data 2825 1451 213 Sheets), or were evaluated by Koning [Ko97]. 2825 1451 214 2825 1451 215 Only 2 measurements exist for neutron-induced emission spectra 2825 1451 216 above 20 MeV for 58Ni: the (n,x alpha) data by Haight et al 2825 1451 217 [Ha97], and (n,xp) data by Ullman et al [Ul83]. Some of the level2825 1451 218 density parameters were adjusted to give a good description of 2825 1451 219 these data. Our starting point was the Gilbert-Cameron analysis 2825 1451 220 of Fu [Fu96], who studied the extreme sensitivity of calculated 2825 1451 221 cross sections on level densities for an IAEA CRP. Fu matched the 2825 1451 222 experimental D-0 value (14.4 keV) in 55Fe, and experimental 2825 1451 223 neutron, alpha, and proton emission data, by modifying the level 2825 1451 224 density a parameters. We modified Fu's 58Ni level density by 5% to2825 1451 225 a=6.5 to better describe Haight's data at 14 MeV. Above 14 MeV, 2825 1451 226 where (n,na) and (n,pa) become important, we increased the default2825 1451 227 level density a parameters in 54Fe and 54Mn by 7.5% to obtain an 2825 1451 228 improved agreement of the Haight data in the 40-50 MeV range (no 2825 1451 229 direct experimental information constrains these level densities).2825 1451 230 See Ref. [Ch97] for benchmark comparisons of the evaluation with 2825 1451 231 measured data. 2825 1451 232 2825 1451 233 *************************************************************** 2825 1451 234 2825 1451 235 REFERENCES 2825 1451 236 2825 1451 237 [Be71] F.D. Becchetti, Jr., and G.W. Greenlees in 2825 1451 238 "Polarization Phenomena in Nuclear Reactions," (Ed: H.H. 2825 1451 239 Barschall and W. Haeberli, The University of Wisconsin Press, 2825 1451 240 1971) p.682 2825 1451 241 [Ca96] R. F. Carlson, Atomic Data and Nuclear Data Tables, 63, 2825 1451 242 93(1996). 2825 1451 243 [Ch93] M.B. Chadwick and P.G. Young, Phys.Rev. C 47, 2255 (1993) 2825 1451 244 [Ch96] M.B. Chadwick, P.G. Young, R.E. MacFarlane, and A.J. 2825 1451 245 Koning, "High-Energy Nuclear Data Libraries for Accelerator- 2825 1451 246 Driven Technologies: Calculational Method for Heavy Recoils," 2825 1451 247 Proc. of 2nd Int. Conf. on Accelerator Driven Transmutation 2825 1451 248 Technology and Applications, Kalmar, Sweden, 3-7 June 1996 2825 1451 249 [Ch97] M. B. Chadwick and P. G. Young, "Model Calculations of 2825 1451 250 n,p + 58,60,61,62,64Ni" in APT PROGRESS REPORT: 1 August - 1 2825 1451 251 September 1997, internal Los Alamos National Laboratory memo T-2825 1451 252 2-97/MS-51, 8 September 1997 from R.E. MacFarlane to L. Waters.2825 1451 253 [Ch99] M.B. Chadwick, P G. Young, G. M. Hale, et al., Los Alamos 2825 1451 254 National Laboratory report, LA-UR-99-1222 (1999) 2825 1451 255 [Ci68] S. Cierjack et al, report KFK-1000 (1968) 2825 1451 256 [Co67] J.L. Cook, H. Ferguson, and A.R. DeL Musgrove, Aust.J. 2825 1451 257 Phys. 20, 477 (1967) 2825 1451 258 [De89] J.P. Delaroche, Y. Wang and J. Rapaport, Phys.Rev.C 39, 2825 1451 259 391 (1989) 2825 1451 260 [Di97] F. Dietrich et al., private communication (1997). 2825 1451 261 [Fr01] S.C. Frankle, R.C. Reedy, and P.G. Young, Los ALamos 2825 1451 262 National Laboratory Report, LA-13812 (2001). 2825 1451 263 [Fu96] C.Y. Fu, "Effects of shape differences in the level 2825 1451 264 densities of three formalisms on calculated cross sections", 2825 1451 265 personal communication, 1996 (to be published by the IAEA). 2825 1451 266 [Gi65] A. Gilbert and A.G.W. Cameron, Can.J.Phys. 43, 1446 (1965)2825 1451 267 [Gu85] P.P. Guss et al, Nucl.Phys. A438, 187 (1985) 2825 1451 268 [Ha82] R.C. Harper and W.L. Alford, J.Phys.G. 8, 153 (1982) 2825 1451 269 [Ha97] R.C. Haight, F.B. Bateman, S.M. Sterbenz et al., Nuclear 2825 1451 270 Data for Science and Technol., Proc. Conf. Trieste, Italy, May 2825 1451 271 1997, Vol. I (Edit. Compositori, Bologna, Italy, 1997) p. 603 2825 1451 272 [Ka77] C. Kalbach, Z.Phys.A 283, 401 (1977) 2825 1451 273 [Ka85] C. Kalbach, Los Alamos National Laboratory report 2825 1451 274 LA-10248-MS (1985) 2825 1451 275 [Ka88] C. Kalbach, Phys.Rev.C 37, 2350 (1988); see also 2825 1451 276 C. Kalbach and F. M. Mann, Phys.Rev.C 23, 112 (1981) 2825 1451 277 [Ko90] J. Kopecky and M. Uhl, Phys.Rev.C 41, 1941 (1990) 2825 1451 278 [Ko97] A. Koning and J.P. Delaroche, private communication. 2825 1451 279 [La83] D.C. Larson et al, report ORNL-TM-8203 (1983) 2825 1451 280 [Lo74] J.M.Lohr and W.Haeberli, Nucl.Phys. A232, 381 (1974) 2825 1451 281 [Mc66] L. McFadden and G.R. Satchler, Nucl.Phys. 84, 177 (1966) 2825 1451 282 [Mu81] S.F. Mughabghab, M. Divadeenam and N.E. Holden, "Neutron 2825 1451 283 Cross Sections", Vol. 1, Part A (Academic Press, 1981) 2825 1451 284 [Pe73] F.G. Perey, private communicatiopn (1973) [EXFOR 10342] 2825 1451 285 [Pe88] Pedroni et al, Phys. Rev. C38, 2052(1988). 2825 1451 286 [Po81] W. Poenitz, Proc. Conf. on Nuclear Data Evaluation Methods2825 1451 287 and Procedures, Brookhaven National Laboratory Report BNL-NCS- 2825 1451 288 51363, p.249(1981). 2825 1451 289 [Ra96] J. Raynal, "Notes on ECIS94", Service de Physique 2825 1451 290 Theorique, Saclay, France (personal communication through A. J.2825 1451 291 Koning, 1996). 2825 1451 292 [Sc73] W. Schimmerling et al., Phys. Rev. C7, 248(1973). 2825 1451 293 [Sm91] D.L. Smith, "Probability, Statistics, and Data Uncertainty2825 1451 294 in Nuclear Science and Technology", American Nuclear Society 2825 1451 295 (1991). 2825 1451 296 [Sm92] A.B. Smith et al., J. Phys. G. 18, 629(1992) 2825 1451 297 [Tu73] A.I. Tutubalin et al., Neutron Physics, Proc. Conf., Kiev,2825 1451 298 Ukraine, 1973, Vol. 3 [EXFOR 40417] p. 62 2825 1451 299 [Ul83] J.J. Ullmann, F.P. Brady, C.M. Castaneda et al., Nucl. 2825 1451 300 Phys. A427, 493 (1984) 2825 1451 301 [We96] H.P. Wellisch and D. Axen, Phys.Rev.C 54, 1329 (1996) 2825 1451 302 [Ya79] Y. Yamanouti, J. Rapaport, S.M. Grimes et al, Nuclear 2825 1451 303 Cross Sections for Technology, Proc. Conf., Knoxville, TN, 2825 1451 304 1979, NBS Special Publication 594 (1980) [EXFOR 10953] 2825 1451 305 [Yo92] P.G. Young, E.D. Arthur, and M.B. Chadwick, report 2825 1451 306 LA-12343-MS (1992) 2825 1451 307 2825 1451 308 **************************************************************** 2825 1451 309 2825 1451 310 ENDF/B-VI MOD 2 Revision, October 1989, D.C. Larson, 2825 1451 311 C.M. Perey, D.M. Hetrick, and C.Y. Fu (ORNL) 2825 1451 312 2825 1451 313 1. Capture widths corrected for 58.7 and 439.52 keV resonances. 2825 1451 314 2. The elastic transformation matrix was removed. 2825 1451 315 3. Fixed typo in minimum energy in MF=6, MT=51 2825 1451 316 2825 1451 317 **************************************************************** 2825 1451 318 2825 1451 319 ENDF/B-VI MOD 1 Evaluation, October 1989, D.C. Larson, 2825 1451 320 C.M. Perey, D.M. Hetrick, and C.Y. Fu (ORNL) 2825 1451 321 2825 1451 322 THIS WORK EMPLOYED NUCLEAR MODEL CODES INCLUDING THE 2825 1451 323 DISTORTED WAVE BORN APPROXIMATION (DWBA) PROGRAM DWUCK (1) 2825 1451 324 AND THE HAUSER-FESHBACH CODE TNG (2,3,4). THE TNG CODE PROVIDES 2825 1451 325 ENERGY AND ANGULAR DISTRIBUTIONS OF PARTICLES EMITTED IN THE 2825 1451 326 COMPOUND AND PRE-COMPOUND REACTIONS, ENSURES CONSISTENCY AMONG ALL2825 1451 327 REACTIONS, AND MAINTAINS ENERGY BALANCE. DETAILS PERTINENT TO THE 2825 1451 328 CONTENTS OF THIS EVALUATION AND EXTENSIVE COMPARISONS OF 2825 1451 329 CALCULATIONS WITH EXPERIMENTAL DATA CAN BE FOUND IN REFERENCE (5).2825 1451 330 2825 1451 331 ----- DESCRIPTION OF FILES 2825 1451 332 (MF-MT) 2825 1451 333 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2825 1451 334 2-151 RESONANCE PARAMETERS ARE USED EXCLUSIVELY TO PROVIDE THE 2825 1451 335 TOTAL, SCATTERING AND CAPTURE CROSS SECTIONS FROM 1.E-5 EV2825 1451 336 TO 812 KEV, EXCEPT FOR CAPTURE FROM 450-812 KEV. THE 2825 1451 337 RESONANCE PARAMETERS ARE TAKEN FROM AN 2825 1451 338 EXTENSIVE RESONANCE PARAMETER ANALYSIS OF TRANSMISSION, 2825 1451 339 SCATTERING AND CAPTURE DATA (6). NEGATIVE ENERGY 2825 1451 340 RESONANCES HAVE BEEN USED TO GIVE THE CORRECT THERMAL 2825 1451 341 VALUES. THE SCATTERING CROSS SECTION IS GIVEN COMPLETELY 2825 1451 342 BY THE RESONANCE PARAMETERS FROM 1.E-5 TO 812 KEV, BUT FOR2825 1451 343 THE CAPTURE CROSS SECTION, AVERAGE RESONANCE PARAMETERS 2825 1451 344 USED FROM 450 TO 812 KEV. THUS, THERE IS A BACKGROUND 2825 1451 345 CONTRIBUTION IN 3/102 FROM 450 TO 812 KEV TO ACCOUNT FOR 2825 1451 346 THE SMALL DIFFERENCE IN CAPTURE CROSS SECTION FROM THE 2825 1451 347 AVERAGE RESONANCE PARAMETERS AND THE AVERAGED EXPERIMENTAL2825 1451 348 DATA (6). THE REICH-MOORE CODE SAMMY (7) WAS USED FOR THE2825 1451 349 RESONANCE PARAMETER ANALYSIS. 2825 1451 350 THUS, THE THERMAL CROSS SECTIONS ARE GIVEN BY THE 2825 1451 351 RESONANCE PARAMETERS AND HAVE VALUES: TOTAL 29.4 B, 2825 1451 352 ELASTIC SCATTERING 24.8 B, AND CAPTURE 4.62 B. 2825 1451 353 NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2825 1451 354 OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE 2825 1451 355 PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON 2825 1451 356 A FINER ENERGY GRID THAN GIVEN IN 4/2. 2825 1451 357 3-1 THE TOTAL CROSS SECTION WAS OBTAINED FROM .812 TO 20 MEV 2825 1451 358 BY ANALYSIS OF THE SAME HIGH RESOLUTION MEASUREMENT 2825 1451 359 USED FOR THE RESONANCE PARAMETER ANALYSIS IN 2/151. DATA 2825 1451 360 WERE BINNED AND COMPARED WITH ENERGY AVERAGED DATA FROM 2825 1451 361 ARGONNE (8) AND OTHER DATA FROM CSISRS, AND GOOD 2825 1451 362 AGREEMENT WAS FOUND. 2825 1451 363 3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY 2825 1451 364 SUBTRACTING THE NONELASTIC FROM THE TOTAL 2825 1451 365 3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22, 2825 1451 366 3-28, 3-102, 3-103, 3-104, AND 3-107. 2825 1451 367 3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, .. 2825 1451 368 .., 3-58, AND 3-91 2825 1451 369 3-16 (N,2N) CROSS SECTIONS WERE TAKEN FROM THE EVALUATION 2825 1451 370 OF 58NI(N,2N)57NI CROSS SECTIONS BY PAVLIK AND 2825 1451 371 WINKLER (9). THESE CROSS SECTIONS WERE SLIGHTLY LARGER 2825 1451 372 THAN THE TNG CALCULATIONS. (SEE (N,NP) BELOW). 2825 1451 373 3-22 (N,NA) + (N,AN) CROSS SECTIONS WERE CALCULATED BY THE TNG 2825 1451 374 CODE (2,3,4,5). NO DATA AVAILABLE OTHER THAN A EMISSION. 2825 1451 375 3-28 (N,NP) + (N,PN) CROSS SECTIONS WERE CALCULATED BY THE TNG 2825 1451 376 CODE (2,3,4,5) BUT MODIFIED ABOVE EINC OF 13.0 MEV TO FIT 2825 1451 377 THE DATA OF PAVLIK ET AL. (10). THE MODIFICATION OF THE 2825 1451 378 TNG CALCULATION FOR (N,NP) CANCELED OUT THE DIFFERENCE 2825 1451 379 BETWEEN THE TNG CALCULATION FOR (N,2N) AND THE ACTUAL 2825 1451 380 (N,2N) USED (SEE ABOVE) SO THAT THE TNG CALCULATED 2825 1451 381 NONELASTIC CROSS DID NOT CHANGE. 2825 1451 382 3-51 TO 3-58 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE 2825 1451 383 FROM TNG (2,3,4,5) WHICH INCLUDES DIRECT INTERACTION 2825 1451 384 CROSS SECTIONS FROM DWUCK (1) CALCULATIONS. EXTENSIVE 2825 1451 385 COMPARISONS WITH EXPERIMENTAL DATA USED IN THE EVALUATION 2825 1451 386 PROCESS ARE SHOWN IN (5). 2825 1451 387 3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM (TNG 2825 1451 388 CALCULATED). GUIDANCE FROM (N,XN) EMISSION DATA (5). 2825 1451 389 3-102 (N,G) CAPTURE CROSS SECTION IS PROVIDED ONLY BY RESONANCE 2825 1451 390 PARAMETERS FROM 1.E-5 EV TO 450 KEV. FROM 450 TO 812 KEV 2825 1451 391 A SMALL BACKGROUND FILE IS GIVEN IN 3/102 TO COMBINE WITH 2825 1451 392 THE 2/151 RESULTS. TNG CALCULATIONS WERE NORMALIZED 2825 1451 393 TO THE RESONANCE REGION RESULTS BETWEEN 100-812 KEV, 2825 1451 394 AND USED FROM 812 KEV TO 20 MEV. 2825 1451 395 3-103 (N,P) CROSS SECTIONS UP TO 6 MEV WERE TAKEN FROM THE 2825 1451 396 GLUCS (12) CALCULATION IN WHICH THIS REACTION WAS STUDIED 2825 1451 397 SIMULTANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS 2825 1451 398 SECTIONS (13). FROM 6 TO 13 MEV A LINE WAS DRAWN 2825 1451 399 THROUGH DATA (SEVERAL MEASURED DATA SETS DISAGREE AND A 2825 1451 400 COMPROMISE WAS CHOSEN). ABOVE 13 MEV, TNG CALC. WERE USED 2825 1451 401 WHICH COMPARED VERY WELL WITH RECENT MEASUREMENTS (5). 2825 1451 402 3-104 (N,D) CROSS SECTION - TAKEN FROM ENDF/B-V (11) WHICH 2825 1451 403 AGREED WELL WITH AVAILABLE DATA. 2825 1451 404 3-107 (N,A) CROSS SECTIONS WERE CALCULATED BY THE 2825 1451 405 TNG CODE (2,3,4,5) AND MODIFIED BETWEEN EINC FROM 7.0 TO 2825 1451 406 13 MEV TO BETTER FIT THE RATIO DATA OF WATTECAMPS (14). 2825 1451 407 4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS FOR ELASTIC 2825 1451 408 SCATTERING WERE REVIEWED AND ADOPTED FROM ENDF/B-V (11). 2825 1451 409 IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY 2825 1451 410 THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE 2825 1451 411 PARAMETERS IN 2/151. 2825 1451 412 6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2825 1451 413 NEUTRON AND 57NI RESIDUAL, AND ENERGY DEPENDENT YIELDS 2825 1451 414 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2825 1451 415 RAY; TNG CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR2825 1451 416 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2825 1451 417 THE OUTGOING NEUTRON). (N,XN) D-D EMISSION DATA HEAVILY 2825 1451 418 USED TO BENCHMARK THE TNG CALCULATIONS (5). 2825 1451 419 6-22 (N,NA) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2825 1451 420 NEUTRON, ALPHA, AND 54FE RESIDUAL, AND ENERGY DEPENDENT 2825 1451 421 YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE 2825 1451 422 GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2825 1451 423 FOR EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY 2825 1451 424 FOR THE OUTGOING NEUTRON; ISOTROPY IS ASSUMED FOR THE 2825 1451 425 ALPHA AND RESIDUAL). (N,XA) D-D EMISSION DATA HEAVILY USED2825 1451 426 TO BENCHMARK THE TNG CALCULATIONS (5). 2825 1451 427 6-28 (N,NP) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2825 1451 428 NEUTRON, P, AND 57CO RESIDUAL, AND ENERGY DEPENDENT YIELD 2825 1451 429 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2825 1451 430 RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR 2825 1451 431 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2825 1451 432 THE OUTGOING NEUTRON). (N,XP) D-D EMISSION DATA HEAVILY 2825 1451 433 USED TO BENCHMARK THE TNG CALCULATIONS (5). 2825 1451 434 6-51 THROUGH 6-58 INELASTIC SCATTERING EXCITING LEVELS; EACH 2825 1451 435 SECTION INCLUDES SIMPLE CONSTANT YIELDS FOR THE NEUTRON 2825 1451 436 AND 58NI RESIDUAL; ANGULAR DISTRIBUTIONS ARE GIVEN FOR 2825 1451 437 THE OUTGOING NEUTRON (LEGENDRE COEFFICIENTS COMPUTED 2825 1451 438 BY DWUCK (1) AND TNG (2,3,4,5)). EXTENSIVE COMPARISONS 2825 1451 439 WITH ANGULAR DISTRIBUTION DATA ARE GIVEN IN (5). 2825 1451 440 6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES 2825 1451 441 SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 58NI 2825 1451 442 RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG 2825 1451 443 CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; TNG 2825 1451 444 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2825 1451 445 FOR EACH (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR THE 2825 1451 446 OUTGOING NEUTRON). (N,XN) D-D EMISSION DATA HEAVILY USED 2825 1451 447 TO BENCHMARK THE TNG CALCULATIONS (5). 2825 1451 448 6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P 2825 1451 449 AND 58CO RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2825 1451 450 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2825 1451 451 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2825 1451 452 PRODUCT. (N,XP) D-D EMISSION DATA HEAVILY USED TO BENCH- 2825 1451 453 MARK THE TNG CALCULATIONS (5). 2825 1451 454 6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A 2825 1451 455 AND 55FE RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2825 1451 456 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2825 1451 457 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2825 1451 458 PRODUCT. (N,XA) D-D EMISSION DATA HEAVILY USED TO BENCH- 2825 1451 459 MARK THE TNG CALCULATIONS (5). 2825 1451 460 12-51 THROUGH 12-58 BRANCHING RATIOS FOR THE LEVELS, COMPILED 2825 1451 461 BY HETRICK ET AL. (5), ARE GIVEN. 2825 1451 462 12-102 (N,G) CAPTURE; MULTIPLICITIES WERE TNG CALCULATED. 2825 1451 463 14-51 THROUGH 14-58 AND 14-102 GAMMA RAY ANGULAR DISTRIBUTIONS 2825 1451 464 ASSUMED TO BE ISOTROPIC. 2825 1451 465 15-102 (N,G) CAPTURE; TNG CALCULATED. 2825 1451 466 -------------------------------------------------------------- 2825 1451 467 UNCERTAINTY FILES 2825 1451 468 ALL NON-DERIVED FILES CONTAIN AN LB=8 COMPONENT, AS 2825 1451 469 REQUIRED BY ENDF/B-VI FORMATS 2825 1451 470 2825 1451 471 33-1 TOTAL UNCERTAINTIES GIVEN AS DERIVED FROM 1E-5 TO 100 EV 2825 1451 472 EXPLICIT FROM 100 EV TO 20 MEV, USING LB=0,1 AND 8. 2825 1451 473 33-2 EXPLICIT FROM 1E-5 10 100 EV, DERIVED FROM 100EV TO 20 MEV2825 1451 474 33-3 DERIVED FROM 1.E-5 TO 450 KEV, EXPLICIT USING LB=1,8 FROM 2825 1451 475 450 KEV TO 20 MEV 2825 1451 476 33-4 DERIVED FROM THRESHOLD TO 20 MEV. 2825 1451 477 33-16 (N,2N) COVARIANCES WERE TAKEN FROM THE EVALUATION OF 2825 1451 478 PAVLIK AND WINKLER (9). 2825 1451 479 33-22 (N,NA) UNCERTAINTIES ESTIMATED FROM CALCULATION AND DATA 2825 1451 480 33-28 (N,NP) COVARIANCES - PAVLIK ET AL.'S (10) DATA USED AS A 2825 1451 481 GUIDE. 2825 1451 482 33-51-91 INELASTIC SCATTERING UNCERTAINTIES ESTIMATED FROM DATA 2825 1451 483 AND CALCULATIONS. 2825 1451 484 33-102 CAPTURE UNCERTAINTIES ESTIMATED FROM THERMAL VALUE AT LOW 2825 1451 485 ENERGIES, BINNED DATA IN THE RESONANCE REGION, AND CALCU- 2825 1451 486 LATIONS FROM TNG FROM 450 KEV TO 20 MEV. 2825 1451 487 33-103 (N,P) COVARIANCES WERE TAKEN FROM THE GLUCS (12) 2825 1451 488 CALCULATION IN WHICH THIS REACTION WAS STUDIED 2825 1451 489 SIMULTANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS 2825 1451 490 SECTIONS (13). 2825 1451 491 33-104 (N,D) COVARIANCES - CSISRS DATA USED AS A GUIDE. 2825 1451 492 33-107 (N,A) COVARIANCES - CSISRS DATA USED AS A GUIDE. 2825 1451 493 2825 1451 494 **************************************************************** 2825 1451 495 2825 1451 496 REFERENCES 2825 1451 497 2825 1451 498 (1) P.D. Kunz, "Distorted Wave Code DWUCK72," Univ. of 2825 1451 499 Colorado, unpublished (1972) 2825 1451 500 (2) C.Y. Fu, Oak Ridge NAtional Laboratory report ORNL/TM-7042 2825 1451 501 (1980) 2825 1451 502 (3) C.Y Fu, Neutron Cross Sections from 10 to 50 MeV, Proc. Symp.2825 1451 503 Upton, NY, May 1980, Brookhaven report BNL-NCS-51425 (1980) 2825 1451 504 p. 675 2825 1451 505 (4) K. Shibata and C.Y. Fu, Oak Ridge National Laboratory report 2825 1451 506 ORNL/TM-10093 (1986) 2825 1451 507 (5) D.M. Hetrick, C.Y. Fu, and D.C. Larson, Oak Ridge National 2825 1451 508 Laboratory report ORNL/TM-10219 [ENDF-344] (1987) 2825 1451 509 (6) C.M. Perey, F.G. Perey, J.A. Harvey, et al., Oak Ridge 2825 1451 510 Laboratort report ORNL/TM-10841, IN PREPARATION 2825 1451 511 (7) N.M. Larson and F.G. Perey, Oak Ridge National Laboratory 2825 1451 512 reports ORNL/TM-7485 (1980); ORNL/TM-9179 (1984); 2825 1451 513 ORNL/TM-9179/R1 (1985); ORNL/TM-9179/R2 (1988) 2825 1451 514 (8) C. Budtz-Jorgensen, P.T. Guenther, A.B. Smith and J.F. Whalen2825 1451 515 Zeit.Phys A 306, 265 (1982) and report ANL/NDM-61 (1982) 2825 1451 516 (9) A. Pavlik and G. Winkler, International Nuclear 2825 1451 517 Committee report INDC(AUS)-9/L (International Atomic Energy 2825 1451 518 Agency, 1983) 2825 1451 519 (10) A. Pavlik, G. Winkler, M. Uhl et al., Nucl.Sci.Eng. 90, 186 2825 1451 520 (1985) 2825 1451 521 (11) M. Divadeenam, Brookhaven National Laboratory report 2825 1451 522 BNL-NCS-51346 [ENDF-294] (1979) 2825 1451 523 (12) D.M. Hetrick and C.Y. Fu, Oak Ridge National Laboratory 2825 1451 524 report ORNL/TM-7341 [ENDF-303] (1980) 2825 1451 525 (13) C.Y. Fu and D.M. Hetrick, ASTM-Euratom Symp. on Reactor 2825 1451 526 Dosimetry, Gaithersburg, MD, March 1982, National Bureau of 2825 1451 527 Standards, p. 877 2825 1451 528 (14) E. Wattecamps, GEEL, Belgium, private communication (1987) 2825 1451 529 2825 1451 530 ************************ C O N T E N T S *********************** 2825 1451 531 ***************** Program LINEAR (VERSION 2004-1) ***************2825 1451 532 For All Data Greater than 1.0000E-10 barns in Absolute Value 2825 1451 533 Data Linearized to Within an Accuracy of .100000000 per-cent 2825 1451 534 ***************** Program RECENT (VERSION 2004-1) ***************2825 1451 535 for All Data Greater than 1.0000E-10 barns in Absolute Value 2825 1451 536 Data Linearized to within an Accuracy of .100000000 per-cent 2825 1451 537 ***************** Program FIXUP (Version 2004-1) ****************2825 1451 538 Corrected ZA/AWR in All Sections-----------------------------Yes 2825 1451 539 Corrected Thresholds-----------------------------------------No 2825 1451 540 Extended Cross Sections to 20 MeV----------------------------No 2825 1451 541 Allow Cross Section Deletion---------------------------------No 2825 1451 542 Allow Cross Section Reconstruction---------------------------Yes 2825 1451 543 Make All Cross Sections Non-Negative-------------------------Yes 2825 1451 544 Delete Energies Not in Ascending Order-----------------------Yes 2825 1451 545 Deleted Duplicate Points-------------------------------------Yes 2825 1451 546 Check for Ascending MAT/MF/MT Order--------------------------Yes 2825 1451 547 Check for Legal MF/MT Numbers--------------------------------Yes 2825 1451 548 Allow Creation of Missing Sections---------------------------No 2825 1451 549 Allow Insertion of Energy Points-----------------------------No 2825 1451 550 Create Uniform Energy Grid-----------------------------------No 2825 1451 551 Delete Section if Cross Section =0 at All Energies-----------Yes 2825 1451 552 **************** Program DICTIN (VERSION 2004-1) ****************2825 1451 553 1 451 631 42825 1451 554 2 151 489 22825 1451 555 3 1 50722 32825 1451 556 3 2 50697 32825 1451 557 3 3 48953 32825 1451 558 3 4 16 12825 1451 559 3 5 9 32825 1451 560 3 16 10 12825 1451 561 3 22 7 12825 1451 562 3 28 7 12825 1451 563 3 51 13 12825 1451 564 3 52 12 12825 1451 565 3 53 12 12825 1451 566 3 54 12 12825 1451 567 3 55 12 12825 1451 568 3 56 11 12825 1451 569 3 57 11 12825 1451 570 3 58 11 12825 1451 571 3 91 11 12825 1451 572 3 102 48929 42825 1451 573 3 103 14 12825 1451 574 3 104 12 12825 1451 575 3 107 15 12825 1451 576 4 2 3747 32825 1451 577 6 5 13047 32825 1451 578 6 16 233 12825 1451 579 6 22 401 12825 1451 580 6 28 492 12825 1451 581 6 51 47 22825 1451 582 6 52 41 12825 1451 583 6 53 41 12825 1451 584 6 54 7 12825 1451 585 6 55 7 12825 1451 586 6 56 41 12825 1451 587 6 57 41 12825 1451 588 6 58 7 12825 1451 589 6 91 1233 12825 1451 590 6 103 1112 12825 1451 591 6 107 1077 12825 1451 592 12 51 3 12825 1451 593 12 52 3 12825 1451 594 12 53 3 12825 1451 595 12 54 3 12825 1451 596 12 55 3 12825 1451 597 12 56 3 12825 1451 598 12 57 3 12825 1451 599 12 58 3 12825 1451 600 12 102 985 42825 1451 601 14 51 1 12825 1451 602 14 52 1 12825 1451 603 14 53 1 12825 1451 604 14 54 1 12825 1451 605 14 55 1 12825 1451 606 14 56 1 12825 1451 607 14 57 1 12825 1451 608 14 58 1 12825 1451 609 14 102 1 42825 1451 610 15 102 239 12825 1451 611 33 1 26 12825 1451 612 33 2 14 12825 1451 613 33 3 16 12825 1451 614 33 4 9 12825 1451 615 33 16 39 12825 1451 616 33 22 14 12825 1451 617 33 28 12 12825 1451 618 33 51 12 12825 1451 619 33 52 14 12825 1451 620 33 53 14 12825 1451 621 33 54 14 12825 1451 622 33 55 14 12825 1451 623 33 56 12 12825 1451 624 33 57 12 12825 1451 625 33 58 12 12825 1451 626 33 91 10 12825 1451 627 33 102 21 12825 1451 628 33 103 87 12825 1451 629 33 104 12 12825 1451 630 33 107 16 12825 1451 631 2825 1 0 632 2825 0 0 633 2.80580E+4 5.74380E+1 0 0 1 02825 2151 634 2.80580E+4 1.00000E+0 0 0 1 02825 2151 635 1.00000E-5 8.12000E+5 1 3 0 12825 2151 636 0.0 6.40000E-1 1 0 3 32825 2151 637 5.74380E+1 6.30350E-1 0 0 402 672825 2151 638 -78318.0000 .500000000 40685.0000 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