13-Al- 27 ENDF/B-VI, Processed by Red Cullen using PREPRO2004 6000 0 0 0 1.30270E+4 2.67497E+1 0 0 0 41325 1451 1 0.0 0.0 0 0 0 61325 1451 2 1.00000E+0 1.50000E+8 8 0 10 61325 1451 3 0.0 0.0 1 0 452 2731325 1451 4 13-Al- 27 LANL EVAL-FEB97 M.B.CHADWICK & P.G.YOUNG 1325 1451 5 Ch97,Ch99 DIST-SEP 1 REV3- 20010926 1325 1451 6 ----ENDF/B-VI MATERIAL 1325 REVISION 2 1325 1451 7 -----INCIDENT NEUTRON DATA 1325 1451 8 ------ENDF-6 FORMAT 1325 1451 9 1325 1451 10 **************************************************************** 1325 1451 11 1325 1451 12 ENDF/B-VI MOD 4 Revision, May 2000, S.C.Frankle, R.C.Reedy, 1325 1451 13 P.G.Young (LANL) 1325 1451 14 1325 1451 15 The secondary gamma-ray spectrum for radiative capture (MF 12, 1325 1451 16 MT 102) has been updated for new experimental data at incident 1325 1451 17 neutron energies up to 10 keV, with a smooth transition to the 1325 1451 18 previous MOD 3 evaluation between 10 and 100 keV. The MT=102 1325 1451 19 evaluation is unchanged above 100 keV. The Q-value for radiative 1325 1451 20 capture was updated in File 3. Details of these changes are 1325 1451 21 described in Frankel et al. [Fr2001]. 1325 1451 22 1325 1451 23 **************************************************************** 1325 1451 24 1325 1451 25 ENDF/B-VI MOD 3 Evaluation, February 1997, M.B. Chadwick and 1325 1451 26 P.G. Young (LANL) 1325 1451 27 1325 1451 28 Los Alamos LA150 Library, produced with FKK/GNASH/GSCAN code 1325 1451 29 in cooperation with ECN Petten. 1325 1451 30 1325 1451 31 This evaluation provides a complete representation of the 1325 1451 32 nuclear data needed for transport, damage, heating, 1325 1451 33 radioactivity, and shielding applications over the incident 1325 1451 34 neutron energy range from 1.0E-11 to 150 MeV. The discussion 1325 1451 35 here is divided into the region below and above 20 MeV. 1325 1451 36 1325 1451 37 INCIDENT NEUTRON ENERGIES < 20 MeV 1325 1451 38 1325 1451 39 Below 20 MeV the evaluation is based completely on the ENDF/B- 1325 1451 40 VI.1 (Release 3) evaluation by Young [Yo1994]. 1325 1451 41 1325 1451 42 INCIDENT NEUTRON ENERGIES > 20 MeV 1325 1451 43 1325 1451 44 The ENDF/B-VI Release 3 evaluation extends to 40 MeV and 1325 1451 45 includes cross sections and energy-angle data for all 1325 1451 46 significant reactions. The present evauation utilizes a more 1325 1451 47 compact composite reaction spectrum representation above 20 MeV 1325 1451 48 in order to reduce the length of the file. No essential data for 1325 1451 49 applications is lost with this representation. Additionally, we 1325 1451 50 have modified the neutron reaction cross sections slightly to 1325 1451 51 improve agreement with data above 20 MeV. 1325 1451 52 The evaluation above 20 MeV utilizes MF=6, MT=5 to represent 1325 1451 53 all reaction data. Production cross sections and emission 1325 1451 54 spectra are given for neutrons, protons, deuterons, tritons, 1325 1451 55 alpha particles, gamma rays, and all residual nuclides produced 1325 1451 56 (A>5) in the reaction chains. To summarize, the ENDF sections 1325 1451 57 with non-zero data above En = 20 MeV are: 1325 1451 58 1325 1451 59 MF=3 MT= 1 Total Cross Section 1325 1451 60 MT= 2 Elastic Scattering Cross Section 1325 1451 61 MT= 3 Nonelastic Cross Section 1325 1451 62 MT= 5 Sum of Binary (n,n') and (n,x) Reactions 1325 1451 63 1325 1451 64 MF=4 MT= 2 Elastic Angular Distributions 1325 1451 65 1325 1451 66 MF=6 MT= 5 Production Cross Sections and Energy-Angle 1325 1451 67 Distributions for Emission Neutrons, Protons, 1325 1451 68 Deuterons, and Alphas; and Angle-Integrated 1325 1451 69 Spectra for Gamma Rays and Residual Nuclei That 1325 1451 70 Are Stable Against Particle Emission 1325 1451 71 1325 1451 72 The evaluation is based on nuclear model calculations that 1325 1451 73 have been benchmarked to experimental data, especially for n + 1325 1451 74 Al27 and p + Al27 reactions [Ch1997]. We use the GNASH code system1325 1451 75 [Yo1992], which utilizes Hauser-Feshbach statistical, 1325 1451 76 preequilibrium and direct-reaction theories. Spherical optical 1325 1451 77 model calculations are used to obtain particle transmission 1325 1451 78 coefficients for the Hauser-Feshbach calculations, as well as 1325 1451 79 for the elastic neutron angular distributions. 1325 1451 80 Cross sections and spectra for producing individual residual 1325 1451 81 nuclei are included for reactions that exceed a cross section of 1325 1451 82 approximately 1 nb at any energy. The energy-angle-correlations 1325 1451 83 for all outgoing particles are based on Kalbach systematics 1325 1451 84 [Ka1988]. 1325 1451 85 A model was developed to calculate the energy distributions of 1325 1451 86 all recoil nuclei in the GNASH calculations [Ch1996]. The recoil 1325 1451 87 energy distributions are represented in the laboratory system in 1325 1451 88 MT=5, MF=6, and are given as isotropic in the lab system. All 1325 1451 89 other data in MT=5,MF=6 are given in the center-of-mass system. 1325 1451 90 This method of representation utilizes the LCT=3 option approved 1325 1451 91 at the November, 1996, CSEWG meeting.. 1325 1451 92 Preequilibrium corrections were performed in the course of the 1325 1451 93 GNASH calculations using the exciton model of Kalbach [Ka1977, 1325 1451 94 Ka1985], validated by comparison with calculations using Feshbach,1325 1451 95 Kerman, Koonin (FKK) theory [Ch1993]. Discrete level data from 1325 1451 96 nuclear data sheets were matched to continuum level densities 1325 1451 97 using the formulation of Ignatyuk [Ig1975] and pairing and shell 1325 1451 98 parameters from the Cook [Co1967] analysis. Neutron and charged- 1325 1451 99 particle transmission coefficients were obtained from the 1325 1451 100 optical potentials, as discussed below. Gamma-ray transmission 1325 1451 101 coefficients were calculated using the Kopecky-Uhl model [Ko1990].1325 1451 102 The neutron total cross section was evaluated from available 1325 1451 103 experimental data. From 20 - 40 MeV, the existing ENDF/B-VI.3 1325 1451 104 total cross section evaluation of Young was adopted; from 40 - 1325 1451 105 150 MeV, the evaluation was based primarily on Finlay's 1993 1325 1451 106 measurements [Fi1993]. The optical potential of Petler [Pe1985], 1325 1451 107 specially developed for n+Al elastic scattering, was used for 1325 1451 108 neutrons up to 60 MeV, and above this energy the Madland global 1325 1451 109 potential [Ma1988a] was used. For incident protons, the Petler 1325 1451 110 neutron potential was modified to account for proton scattering 1325 1451 111 up to 60 MeV, and again the Madland global potential was used at 1325 1451 112 higher energies. For deuterons, the potential of Perey and 1325 1451 113 Perey [Pe1963a] was used at all energies, and for tritons the 1325 1451 114 Becchetti and Greenlees potential [Be1971] was adopted. Finally, 1325 1451 115 the potential of Arthur and Young [Ar1980], based on the work of 1325 1451 116 Lemos [Le1972], was used for alpha particles at all energies. 1325 1451 117 DWBA calculations were performed for inelastic scattering to low- 1325 1451 118 lying states using the DWUCK code. 1325 1451 119 While the above optical potentials did describe the 1325 1451 120 experimental neutron and proton nonelastic cross section data 1325 1451 121 fairly well, we modified these theoretical predictions slightly 1325 1451 122 to better agree with the measurements, and renormalized the 1325 1451 123 transmission coefficients accordingly. 1325 1451 124 The present evaluation was greatly facilitated by Benck et 1325 1451 125 al.'s [Be1998] measurements of charged-particle producing 1325 1451 126 reactions on Al for incident neutrons at 63 MeV at Louvain-la- 1325 1451 127 Neuve, Belgium. Since these data represent the only neutron- 1325 1451 128 induced emission spectra above 20 MeV, they have been invaluable 1325 1451 129 for guiding, and testing, our calculations. The proton, triton, 1325 1451 130 and alpha emission spectra in the Benck et al. measurements are 1325 1451 131 described very well. However, our deuteron emission calculations 1325 1451 132 compare poorly with the measurements. Fortunately this has only 1325 1451 133 a small practical impact since deuteron emission is small 1325 1451 134 compared to proton emission, and our calculated emission 1325 1451 135 spectrum approximates the measured deuteron energy deposition 1325 1451 136 (production cross section times average energy) reasonably well, 1325 1451 137 which is important for heating calculations. The combination of 1325 1451 138 equilibrium and preequilibrium reaction mechanisms included in 1325 1451 139 the GNASH code account for the measured data rather well. 1325 1451 140 As an independent validation of our GNASH calculations using 1325 1451 141 the exciton model, we have also performed FKK calculations. This 1325 1451 142 was done by implementing a multistep reaction theory recently 1325 1451 143 developed by Koning and Chadwick, which is particularly suited 1325 1451 144 to the simultaneous calculation of neutron and proton emission. 1325 1451 145 The FKK theory describes the forward-peaking very well, as do 1325 1451 146 our exciton model calculations using the phenomenological 1325 1451 147 Kalbach angular distribution systematics. 1325 1451 148 As additional validation of the models used in our neutron 1325 1451 149 evaluation, extensive comparisons were made to higher energy 1325 1451 150 proton-induced measurements. In particular, the neutron and 1325 1451 151 charged-particle emission spectra measured at the University of 1325 1451 152 Maryland (Kalend et al. and Wu et al.) for 90-MeV protons, by 1325 1451 153 Meier at Los Alamos for 113-MeV protons, and Bertrand and Peelle 1325 1451 154 for 61-MeV protons are all reproduced reasonably by the present 1325 1451 155 analysis [Ch1997]. 1325 1451 156 Another useful test of our model calculations, particularly 1325 1451 157 for radionuclide production, can be made by comparing our 1325 1451 158 theoretical predictions of discrete gamma-ray emission in 1325 1451 159 Al27(n,xngamma) reactions with the recent LANSCE/WNR data taken 1325 1451 160 by Vonach, Haight, and collaborators [Vo1994] using the white 1325 1451 161 neutron source. Preliminary comparisons show reasonably good 1325 1451 162 agreement. 1325 1451 163 1325 1451 164 **************************************************************** 1325 1451 165 1325 1451 166 ENDF/B-VI MOD 2 Revision, August 1996, P. Young (LANL), 1325 1451 167 V. McLane (NNDC) 1325 1451 168 File 1: Thermal values added. . 1325 1451 169 File 3: Corrected interpolation range on first 3 points of MT1 1325 1451 170 and on first 10 points of MT102. 1325 1451 171 1325 1451 172 **************************************************************** 1325 1451 173 1325 1451 174 ENDF/B-VI MOD 1 Evaluation, November 1994, P.G. Young (LANL) 1325 1451 175 1325 1451 176 GENERAL COMMENTS: This evaluation is based on a theoretical 1325 1451 177 analysis that utilizes Hauser-Feshbach statistical theory, with 1325 1451 178 corrections for preequilibrium and stripping processes. 1325 1451 179 Spherical optical model calculations are used to obtain particle 1325 1451 180 transmission coefficients for the Hauser-Feshbach calculations, 1325 1451 181 as well as for the elastic neutron angular distributions. Some 1325 1451 182 data from ENDF/B-VI are retained, in particular, the neutron 1325 1451 183 total cross section below 20 MeV and the radiative capture cross 1325 1451 184 section and photon multipicities below about 100 keV. 1325 1451 185 Cross sections and spectra for individual reactions are 1325 1451 186 included for reactions that exceed a cross section of 1325 1451 187 approximately 1 mb at any energy. Multiplicities and emission 1325 1451 188 energy spectra are given for gamma rays, particles, and recoil 1325 1451 189 nuclei emitted in each reaction, utilizing File 6 of the ENDF/B- 1325 1451 190 6 format [Ro1991]. Energy-angle-correlated spectra are given 1325 1451 191 for all outgoing particles. 1325 1451 192 1325 1451 193 2200 m/sec cross section resonance integral 1325 1451 194 ------------------------ ------------------ 1325 1451 195 Total 1.58 barns 1325 1451 196 Elastic 1.35 barns 1325 1451 197 Capture 0.232 barns 0.134 barns 1325 1451 198 1325 1451 199 HAUSER-FESHBACH STATISTICAL THEORY CALCULATIONS: The GNASH 1325 1451 200 code [Yo1992] was used for all Hauser-Feshbach statistical theory1325 1451 201 calculations. Preequilibrium corrections were performed in the 1325 1451 202 course of the GNASH calculations using the exciton model of 1325 1451 203 Kalbach [Ka1977,Ka1985]. Discrete level data from nuclear data 1325 1451 204 sheets were matched to continuum level densities using the 1325 1451 205 formulation of Ignatyuk [Ig1975] and pairing and shell parameters1325 1451 206 from the Cook [Co1967] analysis. Neutron and charged-particle 1325 1451 207 transmission coefficients were obtained from the optical 1325 1451 208 potentials, as discussed below. Gamma-ray transmission 1325 1451 209 coefficients were calculated using the Kopecky-Uhl model 1325 1451 210 [Ko1990]. 1325 1451 211 Calculations were performed for all significant reactions 1325 1451 212 producing neutrons, protons, deuterons, tritons, alpha 1325 1451 213 particles, and gamma rays for incident neutrons between 1.0E-11 1325 1451 214 and 40 MeV. At the highest energies, approximately 30 compound 1325 1451 215 nuclei had to be included, leading to ~180 reaction paths. 1325 1451 216 The angular distribution systematics by Kalbach [Ka1988] were 1325 1451 217 used to describe the angular distributions for all continuum 1325 1451 218 particles. 1325 1451 219 1325 1451 220 OPTICAL MODEL POTENTIALS: For incident and exiting neutrons, 1325 1451 221 the phenomenological optical potential by Petler et al. [Pe1985],1325 1451 222 based on a microscopic optical model analysis of experimental 1325 1451 223 data, was utilized at all energies. A modified version of 1325 1451 224 Perey's potential [Pe1963b] was used to calculate transmission 1325 1451 225 coefficients for protons below 44 MeV, switching to the Madland 1325 1451 226 potential [Ma1988b] at higher energies. The potential by Perey 1325 1451 227 and Perey [Pe1963b] was utilized to calculate deuteron 1325 1451 228 transmission coefficients for deuterons at all energies. 1325 1451 229 Similarly, a triton potential by Becchetti and Greenlees [Be1971]1325 1451 230 and an alpha potential determined by Arthur and Young [Ar1980] 1325 1451 231 for n + 56Fe reactions were used at all energies for those 1325 1451 232 particles. 1325 1451 233 1325 1451 234 DIRECT REACTIONS: Energy-dependent cross sections of 1325 1451 235 inelastic neutrons from Al27(n,n') direct reactions were 1325 1451 236 calculated using the DWUCK code [Ku1970], normalized to values 1325 1451 237 of the angle-integrated cross sections in ENDF/B-VI at 14 MeV. 1325 1451 238 1325 1451 239 ENDF/B-V CARRYOVERS: The following reactions/data were 1325 1451 240 carried over unchanged from ENDF/B-V: 1325 1451 241 1325 1451 242 MF=2, MT=151: Resonance Parameters 1325 1451 243 Effective scattering radius = 0.32752E-12 cm. (Resonance 1325 1451 244 parameters not given.) 1325 1451 245 1325 1451 246 CALCULATIONAL RESULTS: The MF=3 cross sections and MF=6 1325 1451 247 energy/angle distributions based completely on calculations are: 1325 1451 248 1325 1451 249 MT = 11: (n,2nd) Reaction 1325 1451 250 MT = 16: (n,2n) Reaction 1325 1451 251 MT = 17: (n,3n) Reaction 1325 1451 252 MT = 22: (n,nalpha) Reaction 1325 1451 253 MT = 24: (n,2nalpha) Reaction 1325 1451 254 MT = 28: (n,np) Reaction 1325 1451 255 MT = 29: (n,n2alpha) Reaction 1325 1451 256 MT = 32: (n,nd) Reaction 1325 1451 257 MT = 33: (n,nt) Reaction 1325 1451 258 MT = 41: (n,2np) Reaction 1325 1451 259 MT = 42: (n,3np) Reaction 1325 1451 260 MT = 44: (n,n2p) Reaction 1325 1451 261 MT = 45: (n,npalpha) Reaction 1325 1451 262 MT = 64-89: (n,n') Discrete Level Reactions 1325 1451 263 MT = 91: (n,n') Continuum Reaction 1325 1451 264 MT = 103: (n,p) Reaction (MF=6 only) 1325 1451 265 MT = 104: (n,d) Reaction 1325 1451 266 MT = 105: (n,t) Reaction 1325 1451 267 MT = 107: (n,alpha) Reaction (MF=6 only) 1325 1451 268 MT = 108: (n,2alpha) Reaction 1325 1451 269 MT = 111: (n,2p) Reaction 1325 1451 270 MT = 112: (n,palpha) Reaction 1325 1451 271 MT = 115: (n,pd) Reaction 1325 1451 272 MT = 116: (n,pt) Reaction 1325 1451 273 MT = 117: (n,dalpha) Reaction 1325 1451 274 MT = 649: (n,p) Continuum Reaction 1325 1451 275 MT = 650-669: (n,d) Discrete Level Reactions 1325 1451 276 MT = 699: (n,d) Continuum Reaction 1325 1451 277 MT = 700-710: (n,t) Discrete Level Reactions 1325 1451 278 MT = 749: (n,t) Continuum Reaction 1325 1451 279 MT = 849: (n,alpha) Continuum Reaction 1325 1451 280 1325 1451 281 Kalbach systematics [Ka1988] are used to specify all continuum 1325 1451 282 particle angular distributions. All continuum photon angular 1325 1451 283 distributions are assumed isotropic. 1325 1451 284 1325 1451 285 Additionally, the radioactive nuclei formation data in MF = 8 1325 1451 286 and 9 were obtained directly from the GNASH calculations. 1325 1451 287 1325 1451 288 OTHER REACTIONS: The following reactions are based on 1325 1451 289 combinations of experimental data and theoretical calculations 1325 1451 290 or other techniques: 1325 1451 291 1325 1451 292 MF=3,MT=1: Total Cross Section. 1325 1451 293 Below 20 MeV, carried over from ENDF/B-V. At higher energies 1325 1451 294 based on data of Pe72 and optical model calculation. 1325 1451 295 1325 1451 296 MF=3,MT=2: Elastic Cross Section. 1325 1451 297 Obtained by subtracting sum of nonelastic cross sections from 1325 1451 298 the total. Mainly results from the optical model calculations 1325 1451 299 above 14 MeV. At lower energies the nonelastic cross sections 1325 1451 300 are a combination of experimental data (ENDF/B-V evaluations) 1325 1451 301 and the theoretical calculations. 1325 1451 302 1325 1451 303 MF=3,MT=4: Inelastic Cross Section. 1325 1451 304 Summation of MT=51-91. 1325 1451 305 1325 1451 306 MF=3,MT=51-63: Inelastic Cross Section to Discrete States. 1325 1451 307 Combination of experimental data below 14 MeV [especially (n,n') 1325 1451 308 data of Ki1970 and (n,xgamma) data of Or1971, Di1971, Di1973] 1325 1451 309 and calculated excitation functions, with a rough match to the 1325 1451 310 ENDF/B-V evaluation near 14 MeV. 1325 1451 311 1325 1451 312 MF=3, MT=102: (n,gamma) Cross Section. 1325 1451 313 Below 1 keV, ENDF/B-V was adopted. At higher energies, 1325 1451 314 calculations from GNASH code used, including a semidirect model. 1325 1451 315 1325 1451 316 MF=3,MT=103: (n,p) Cross Section. 1325 1451 317 Taken directly from the International Reactor Dosimetry File 1325 1451 318 IRDF-90 of the IAEA, which was obtained at the Institut fuer 1325 1451 319 Radiumforschung und Kernphysik (IRK) in Vienna [Wa1990]. At 1325 1451 320 higher energies, calculated excitation function were used, 1325 1451 321 normalized to the IRK data at 20 MeV. 1325 1451 322 1325 1451 323 MF=3,MT=107: (n,alpha) Cross Section. 1325 1451 324 Taken directly from the International Reactor Dosimetry File 1325 1451 325 IRDF-90 of the IAEA, which was obtained at the Institut fuer 1325 1451 326 Radiumforschung und Kernphysik (IRK) in Vienna [Wa1990]. At 1325 1451 327 higher energies, calculated excitation function were used, 1325 1451 328 normalized to the IRK data at 20 MeV. 1325 1451 329 1325 1451 330 MF=4, MT=2: Elastic Angular Distributions. 1325 1451 331 ENDF/B-V adopted below En = 6 MeV. At higher energy optical 1325 1451 332 model calculations used (see above). Tabulated distributions 1325 1451 333 given in the center-of-mass system. 1325 1451 334 1325 1451 335 MF=6, MT=51-89: Inelastic Level Neutron & Photon Distributions. 1325 1451 336 For MT=51-62, neutron angular distributions are combination of 1325 1451 337 experimental data and calculated shapes below 14 MeV and are 1325 1451 338 represented by Legendre expansions in the CM system. At higher 1325 1451 339 energies, calculated shapes are used. For MT=63-89, calculated 1325 1451 340 angular distributions are used at all energies. Photon 1325 1451 341 multiplicities based on experimental branching ratios and GNASH 1325 1451 342 calculations. Photon angular distributions assumed isotropic. 1325 1451 343 1325 1451 344 MF=12, MT=102: Radiative Capture Photon Multiplicities. 1325 1451 345 Below 1 keV, ENDF/B-V adopted. At higher energies, based on 1325 1451 346 GNASH calculations. 1325 1451 347 1325 1451 348 MF=15, MT=102: Radiative Capture Photon Energy Distributions. 1325 1451 349 Below 1 keV, ENDF/B-V adopted. At higher energies, based on 1325 1451 350 GNASH calculations. 1325 1451 351 1325 1451 352 ***************************************************************** 1325 1451 353 1325 1451 354 REFERENCES 1325 1451 355 1325 1451 356 [Ar1980] E.D. Arthur and P.G. Young, Proc. Sym. on Neutron Cross 1325 1451 357 Sections from 10 to 50 MeV, 12-14 May 1980, Brookhaven 1325 1451 358 National Laboratory [Eds. M.R. Bhat and S. Pearlstein], 1325 1451 359 report BNL-NCS-51245 (1980) p.731 1325 1451 360 [Be1969] F.D. Becchetti, Jr., and G.W. Greenlees, Phys.Rev. 182, 1325 1451 361 1190 (1969) 1325 1451 362 [Be1971] F.D. Becchetti, Jr., and G.W. Greenlees, Polarization 1325 1451 363 Phenomena in Nuclear Reactions, Proc. Conf. [Ed: H.H.Barschall1325 1451 364 and W.Haeberli] (The University of Wisconsin Press, 1971) 1325 1451 365 p.682 1325 1451 366 [Be1992] O. Bersillon, "SCAT2 - A Spherical Optical Model Code," 1325 1451 367 in Proc. ICTP Workshop on Computation and Analysis of Nuclear 1325 1451 368 Data Relevant to Nuclear Energy and Safety, 10 February-13 1325 1451 369 March, 1992, Trieste, Italy, to be published in World 1325 1451 370 Scientific Press, and Progress Report of the Nuclear Physics 1325 1451 371 Division, Bruyeres-le-Chatel 1977, CEA-N-2037 (1978) p.111 1325 1451 372 [Be1998] S. Benck, I. Slypen, J.P. Meulders, et al., Phys.Rev.C 1325 1451 373 58, 1558 (1998); S. Benck, Ph.D. thesis, Louvain-la-Neuve, 1325 1451 374 Belgium (1997) 1325 1451 375 [Ch1993] M.B. Chadwick and P.G. Young, Phys.Rev. C 47, 2255 1325 1451 376 (1993) 1325 1451 377 [Ch1996] M.B. Chadwick, P.G. Young, R.E. MacFarlane, and A.J. 1325 1451 378 Koning, "High-Energy Nuclear Data Libraries for Accelerator- 1325 1451 379 Driven Technologies: Calculational Method for Heavy Recoils,"1325 1451 380 Proc. of 2nd Int. Conf. on Accelerator Driven Transmutation 1325 1451 381 Technology and Applications, Kalmar, Sweden, 3-7 June 1996. 1325 1451 382 [Ch1997] M.B. Chadwick and P.G. Young, "GNASH Calculations of 1325 1451 383 n,p + 27Al and Benchmarking of Results" in APT Progress 1325 1451 384 Report: 1 January - 1 February 1997, internal Los Alamos 1325 1451 385 National Laboratory memo T-2-97/MS-52, 6 Feb.1997 from R.E. 1325 1451 386 MacFarlane to L. Waters. 1325 1451 387 [Ch1999] M.B. Chadwick, P.G. Young, G.M. Hale, et al., Los Alamos1325 1451 388 National Laboratory report, LA-UR-99-1222 (1999) 1325 1451 389 [Co1967] J.L. Cook, H. Ferguson, and A.R. De L Musgrove, Aust.J. 1325 1451 390 Phys. 20, 477 (1967) 1325 1451 391 [Di1971] J.K. Dickens et al., report ORNL-TM-3284 (1971) 1325 1451 392 [Di1973] J.K. Dickens et al., report ORNL-TM-4232 (1973) 1325 1451 393 [Fi1993] R.W. Finlay, W.P. Abfalterer, G. Fink, et al., Phys.Rev.1325 1451 394 C 47, 237 (1993) 1325 1451 395 [Fr2001] S.C. Frankle, R.C. Reedy, and P.G. Young, Los ALamos 1325 1451 396 National Laboratory Report, LA-13812 (2001). 1325 1451 397 [Ig1975] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov.J. 1325 1451 398 Nucl.Phys. 21, 255 (1975); translation of Yad.Fiz. 21, 485 1325 1451 399 (1975) 1325 1451 400 [Ka1977] C. Kalbach, Z.Phys.A 283, 401 (1977) 1325 1451 401 [Ka1985] C. Kalbach, Los Alamos National Laboratory report 1325 1451 402 LA-10248-MS (1985) 1325 1451 403 [Ka1988] C. Kalbach, Phys.Rev.C 37, 2350 (1988); see also 1325 1451 404 see also C. Kalbach and F.M. Mann, Phys.Rev.C 23, 112 (1981). 1325 1451 405 [Ki1970] W.E. Kinney and F.G. Perey, report ORNL-4516 (1970) 1325 1451 406 [Ko1990] J. Kopecky and M. Uhl, Phys.Rev. C 41, 1941 (1990) 1325 1451 407 [Ku1970] P.D. Kunz, "DWUCK - A Distorted Wave Born Approximation 1325 1451 408 Program," (1970) unpublished 1325 1451 409 [Le1972] O.F. Lemos, "Diffusion Elastique de Particules Alpha 1325 1451 410 de 21 a 29.6 MeV sur des Noyaux de la Region Ti-Zn," Orsay 1325 1451 411 report, Series A, No. 136 (1976) 1325 1451 412 [Ma1988a] D.G. Madland, Proc. OECD/NEANDC Specialist's Mtg. on 1325 1451 413 Preequilibrium Nuclear Reactions, Semmering, Austria, Feb. 1325 1451 414 1988, report NEANDC-245 'U' (1988) p.103 1325 1451 415 [Ma1988b] D.G. Madland, International Atomic Energy Agency report 1325 1451 416 IAEA-TECDOC-483 (1988) p.80 1325 1451 417 [Or1971] V.J. Orphan and C.G. Hoot, Gulf General Atomic report 1325 1451 418 GULF-RT-A10743 (1971) 1325 1451 419 [Pe1963a] C.M. Perey and F.G. Perey, Phys.Rev. 132, 755 (1963) 1325 1451 420 [Pe1963b] F.G. Perey, Phys.Rev. 131, 745 (1963) 1325 1451 421 [Pe1972] F.G. Perey, et al., report ORNL-4823 (1972) 1325 1451 422 [Pe1985] J.S. Petler, M.S. Islam, and R.W. Finlay, Phys.Rev.C 32,1325 1451 423 673 (1985) 1325 1451 424 [Ro1991] P. Rose, Brookhaven National Laboratory informal report 1325 1451 425 BNL-NCS-44945 [ENDF-102, Rev. 10/91] (1991) 1325 1451 426 [Vo1994] H. Vonach, A. Pavlik, M.B. Chadwick, et al., Phys.Rev.C 1325 1451 427 50, 1952 (1994) 1325 1451 428 [Wa1990] M. Wagner, H. Vonach, A. Pavlik, et al., Physics Data 1325 1451 429 13-5 (Fachinformationszentrum Karlsruhe, 1990) 1325 1451 430 [Yo1992] P.G. Young, E.D. Arthur, and M.B. Chadwick, report 1325 1451 431 LA-12343-MS (1992) 1325 1451 432 [Yo1994] P.G. Young, "Evaluation of n + 27Al Cross Sections for 1325 1451 433 the Energy Range 10-5 eV to 40 MeV," ENDF/B-VI Release 3 1325 1451 434 evaluation, Nov., 1994 1325 1451 435 1325 1451 436 ************************* C O N T E N T S ********************** 1325 1451 437 ***************** Program LINEAR (VERSION 2004-1) ***************1325 1451 438 For All Data Greater than 1.0000E-10 barns in Absolute Value 1325 1451 439 Data Linearized to Within an Accuracy of .100000000 per-cent 1325 1451 440 ***************** Program FIXUP (Version 2004-1) ****************1325 1451 441 Corrected ZA/AWR in All Sections-----------------------------Yes 1325 1451 442 Corrected Thresholds-----------------------------------------No 1325 1451 443 Extended Cross Sections to 20 MeV----------------------------No 1325 1451 444 Allow Cross Section Deletion---------------------------------No 1325 1451 445 Allow Cross Section Reconstruction---------------------------Yes 1325 1451 446 Make All Cross Sections Non-Negative-------------------------Yes 1325 1451 447 Delete Energies Not in Ascending Order-----------------------Yes 1325 1451 448 Deleted Duplicate Points-------------------------------------Yes 1325 1451 449 Check for Ascending MAT/MF/MT Order--------------------------Yes 1325 1451 450 Check for Legal MF/MT Numbers--------------------------------Yes 1325 1451 451 Allow Creation of Missing Sections---------------------------No 1325 1451 452 Allow Insertion of Energy Points-----------------------------No 1325 1451 453 Create Uniform Energy Grid-----------------------------------No 1325 1451 454 Delete Section if Cross Section =0 at All Energies-----------Yes 1325 1451 455 **************** Program DICTIN (VERSION 2004-1) ****************1325 1451 456 1 451 729 41325 1451 457 2 151 4 01325 1451 458 3 1 719 31325 1451 459 3 2 617 31325 1451 460 3 3 165 31325 1451 461 3 4 33 11325 1451 462 3 5 12 31325 1451 463 3 16 6 11325 1451 464 3 22 7 11325 1451 465 3 28 8 11325 1451 466 3 32 5 11325 1451 467 3 33 5 11325 1451 468 3 45 5 11325 1451 469 3 51 18 11325 1451 470 3 52 18 11325 1451 471 3 53 18 11325 1451 472 3 54 17 11325 1451 473 3 55 17 11325 1451 474 3 56 16 11325 1451 475 3 57 16 11325 1451 476 3 58 15 11325 1451 477 3 59 15 11325 1451 478 3 60 14 11325 1451 479 3 61 14 11325 1451 480 3 62 14 11325 1451 481 3 63 16 11325 1451 482 3 64 17 11325 1451 483 3 65 14 11325 1451 484 3 66 13 11325 1451 485 3 67 13 11325 1451 486 3 68 13 11325 1451 487 3 69 13 11325 1451 488 3 70 13 11325 1451 489 3 71 12 11325 1451 490 3 72 13 11325 1451 491 3 73 13 11325 1451 492 3 74 12 11325 1451 493 3 75 12 11325 1451 494 3 76 12 11325 1451 495 3 77 12 11325 1451 496 3 78 12 11325 1451 497 3 79 12 11325 1451 498 3 80 12 11325 1451 499 3 81 12 11325 1451 500 3 82 12 11325 1451 501 3 83 11 11325 1451 502 3 84 12 11325 1451 503 3 85 12 11325 1451 504 3 86 11 11325 1451 505 3 87 11 11325 1451 506 3 88 11 11325 1451 507 3 89 11 11325 1451 508 3 91 9 11325 1451 509 3 102 109 41325 1451 510 3 103 25 11325 1451 511 3 104 16 11325 1451 512 3 105 10 11325 1451 513 3 107 22 11325 1451 514 3 108 5 11325 1451 515 3 111 5 11325 1451 516 3 112 5 11325 1451 517 3 117 5 11325 1451 518 3 600 21 11325 1451 519 3 601 20 11325 1451 520 3 602 19 11325 1451 521 3 603 17 11325 1451 522 3 604 17 11325 1451 523 3 605 17 11325 1451 524 3 606 16 11325 1451 525 3 607 16 11325 1451 526 3 608 15 11325 1451 527 3 609 16 11325 1451 528 3 610 15 11325 1451 529 3 611 15 11325 1451 530 3 612 14 11325 1451 531 3 613 14 11325 1451 532 3 614 12 11325 1451 533 3 615 13 11325 1451 534 3 616 12 11325 1451 535 3 617 11 11325 1451 536 3 618 11 11325 1451 537 3 619 11 11325 1451 538 3 649 11 11325 1451 539 3 650 11 11325 1451 540 3 651 9 11325 1451 541 3 652 12 11325 1451 542 3 653 11 11325 1451 543 3 654 11 11325 1451 544 3 655 9 11325 1451 545 3 656 9 11325 1451 546 3 657 9 11325 1451 547 3 658 9 11325 1451 548 3 659 9 11325 1451 549 3 660 9 11325 1451 550 3 661 8 11325 1451 551 3 662 8 11325 1451 552 3 663 7 11325 1451 553 3 664 7 11325 1451 554 3 665 6 11325 1451 555 3 666 6 11325 1451 556 3 667 6 11325 1451 557 3 668 6 11325 1451 558 3 669 6 11325 1451 559 3 699 6 11325 1451 560 3 700 7 11325 1451 561 3 701 7 11325 1451 562 3 702 6 11325 1451 563 3 703 6 11325 1451 564 3 704 6 11325 1451 565 3 705 6 11325 1451 566 3 706 6 11325 1451 567 3 707 6 11325 1451 568 3 708 6 11325 1451 569 3 709 6 11325 1451 570 3 710 5 11325 1451 571 3 749 5 11325 1451 572 3 800 21 11325 1451 573 3 801 19 11325 1451 574 3 802 19 11325 1451 575 3 803 18 11325 1451 576 3 804 17 11325 1451 577 3 805 18 11325 1451 578 3 806 18 11325 1451 579 3 807 17 11325 1451 580 3 808 17 11325 1451 581 3 809 16 11325 1451 582 3 810 16 11325 1451 583 3 811 14 11325 1451 584 3 812 13 11325 1451 585 3 813 12 11325 1451 586 3 814 12 11325 1451 587 3 815 12 11325 1451 588 3 816 12 11325 1451 589 3 817 12 11325 1451 590 3 818 12 11325 1451 591 3 819 11 11325 1451 592 3 849 11 11325 1451 593 4 2 1939 31325 1451 594 6 5 12682 31325 1451 595 6 16 250 11325 1451 596 6 22 462 11325 1451 597 6 28 688 11325 1451 598 6 32 104 11325 1451 599 6 33 64 11325 1451 600 6 45 50 11325 1451 601 6 51 54 11325 1451 602 6 52 54 11325 1451 603 6 53 54 11325 1451 604 6 54 38 11325 1451 605 6 55 44 11325 1451 606 6 56 48 11325 1451 607 6 57 30 11325 1451 608 6 58 52 11325 1451 609 6 59 52 11325 1451 610 6 60 50 11325 1451 611 6 61 52 11325 1451 612 6 62 52 11325 1451 613 6 63 48 11325 1451 614 6 64 22 11325 1451 615 6 65 38 11325 1451 616 6 66 32 11325 1451 617 6 67 30 11325 1451 618 6 68 42 11325 1451 619 6 69 44 11325 1451 620 6 70 36 11325 1451 621 6 71 32 11325 1451 622 6 72 40 11325 1451 623 6 73 34 11325 1451 624 6 74 28 11325 1451 625 6 75 22 11325 1451 626 6 76 38 11325 1451 627 6 77 40 11325 1451 628 6 78 24 11325 1451 629 6 79 36 11325 1451 630 6 80 40 11325 1451 631 6 81 42 11325 1451 632 6 82 24 11325 1451 633 6 83 36 11325 1451 634 6 84 40 11325 1451 635 6 85 32 11325 1451 636 6 86 44 11325 1451 637 6 87 42 11325 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