JEFF-3.1 General Purpose Neutron Library, April 2007 2310 0 0 0 2.004600+4 4.555893+1 0 0 2 12043 1451 1 0.000000+0 0.000000+0 0 0 0 62043 1451 2 1.000000+0 2.000000+8 1 0 10 312043 1451 3 0.000000+0 0.000000+0 0 0 500 1292043 1451 4 20-Ca- 46 NRG EVAL-OCT04 A.J. Koning 2043 1451 5 NRG-2004 DIST-MAY05 REV2-NOV06 20070401 2043 1451 6 ----JEFF-3.1 material 2043 revision 2 2043 1451 7 -----incident neutron data 2043 1451 8 ------endf-6 format 2043 1451 9 ******** Revision April 21, 2006, V.Sinitsa **********************2043 1451 10 2043 1451 11 The total, total elastic and total nonelastic cross sections were 2043 1451 12 zero in the JEFF-3.1 file in the 1.e-5 - 1.e3 eV energy range. 2043 1451 13 This has been fixed by assuming MT2 = 2.9 barn, MT3=MT102 2043 1451 14 and MT1 = MT2 + MT102. 2043 1451 15 2043 1451 16 ***************************** JEFF-3.1 *************************2043 1451 17 ** **2043 1451 18 ** Original data taken from: New evaluation **2043 1451 19 ** **2043 1451 20 ******************************************************************2043 1451 21 2043 1451 22 NRG-2004: n + Ca-46 2043 1451 23 2043 1451 24 Author: A.J. Koning, NRG Petten 2043 1451 25 2043 1451 26 ************** G E N E R A L I N F O R M A T I O N *************2043 1451 27 2043 1451 28 This evaluated data file is based primarily on a theoretical 2043 1451 29 analysis with the nuclear model code TALYS [kon04], version 0.56. 2043 1451 30 The nuclear model parameters of TALYS have been adjusted to 2043 1451 31 reproduce the existing experimental data. The resulting data file 2043 1451 32 provides a complete representation of nuclear data needed for 2043 1451 33 transport, damage, heating, radioactivity, and shielding 2043 1451 34 applications over the incident neutron energy range from 2043 1451 35 1.0E-11 to 200 MeV. 2043 1451 36 2043 1451 37 This file is part of a larger collection of isotopic evaluations, 2043 1451 38 all created by running TALYS with input parameters that do not or 2043 1451 39 slightly deviate from the default values. The mutual quality of 2043 1451 40 these isotopic evaluations is thus relatively consistent. 2043 1451 41 The same set of nuclear models is used and, equally important, 2043 1451 42 the same ENDF-6 formatting procedures for each isotope. We have 2043 1451 43 intended to make this evaluation complete in its description of 2043 1451 44 reaction channels, and use a compact method to store the data. 2043 1451 45 2043 1451 46 For certain reactions and energy ranges TALYS may not be used. 2043 1451 47 This is the case when TALYS is not appropriate, such as for the 2043 1451 48 description of resonances, or when the directly available 2043 1451 49 experimental data is of better quality, as for e.g. low-energy 2043 1451 50 total cross sections. In these cases, we have adopted the best 2043 1451 51 possible data from an existing library, or directly from unfiled 2043 1451 52 experimental data. All transport data for particles, photons and 2043 1451 53 residual nuclides are filed using a combination of MF1,2,3,4 and 2043 1451 54 MF6. This includes cross sections, angular distributions, 2043 1451 55 double-differential spectra, discrete and continuum photon 2043 1451 56 production cross sections, and residual production (activation) 2043 1451 57 cross sections. Moreover, isomeric production data are stored in 2043 1451 58 MF8 and MF10. This evaluation can thus be used as both transport 2043 1451 59 and activation library. The data file has been created 2043 1451 60 automatically using the ENDF-6 format generator TEFAL. 2043 1451 61 2043 1451 62 ##### ORIGIN 2043 1451 63 2043 1451 64 Data < 200 MeV : New evaluation NRG Petten 2043 1451 65 2043 1451 66 All data : Produced with TALYS code 2043 1451 67 2043 1451 68 *************************** T H E O R Y **************************2043 1451 69 2043 1451 70 TALYS is a computer code system for the prediction and analysis 2043 1451 71 of nuclear reactions. TALYS simulates reactions that involve 2043 1451 72 neutrons, gamma-rays, protons, deuterons, tritons, helions and 2043 1451 73 alpha-particles, in the 1 keV - 200 MeV energy range and for 2043 1451 74 target nuclides of mass 12 and heavier. This is achieved by 2043 1451 75 implementing a suite of nuclear reaction models into a single 2043 1451 76 code system. It enables to evaluate nuclear reactions from 2043 1451 77 the unresolved resonance region up to intermediate energies. This 2043 1451 78 evaluation is based on a theoretical analysis that utilizes the 2043 1451 79 optical model, compound nucleus statistical theory, direct 2043 1451 80 reactions and pre-equilibrium processes, in combination with 2043 1451 81 databases and models for nuclear structure. For Ca-46, the 2043 1451 82 following output of TALYS is stored in this data file: 2043 1451 83 2043 1451 84 - Total, elastic and non-elastic cross sections 2043 1451 85 - Elastic scattering angular distributions 2043 1451 86 - Inelastic cross sections to discrete states 2043 1451 87 - Inelastic scattering angular distributions to discrete states 2043 1451 88 - Exclusive channel cross sections, e.g. (n,g), (n,2n), (n,np),.. 2043 1451 89 - Exclusive channel energy spectra 2043 1451 90 - Exclusive channel double-differential spectra 2043 1451 91 - Exclusive gamma production for discrete states and continuum 2043 1451 92 - Isomeric and ground state cross sections 2043 1451 93 - Residual production cross sections 2043 1451 94 - Total particle cross sections, e.g. (n,xn), (n,xp),.. 2043 1451 95 - Total particle energy spectra 2043 1451 96 - Total particle double-differential spectra 2043 1451 97 2043 1451 98 Here follows a short description of the used nuclear models: 2043 1451 99 2043 1451 100 ##### OPTICAL MODEL 2043 1451 101 2043 1451 102 All optical model calculations are performed by ECIS-97 [ray94], 2043 1451 103 in TALYS used as a subroutine. The default optical model 2043 1451 104 potentials (OMP) used are the local and global parameterizations 2043 1451 105 of Koning and Delaroche [kon03]. These are phenomenological OMPs 2043 1451 106 for neutrons and protons which in principle are valid over the 2043 1451 107 1 keV - 200 MeV energy range, though the low energy boundary of 2043 1451 108 validity may differ from nucleus to nucleus (e.g. for the total 2043 1451 109 cross sections, experimental data are included directly in the 2043 1451 110 file for energies below that boundary). Solving the Schroedinger 2043 1451 111 equation with this OMP yields the total cross section, the 2043 1451 112 shape-elastic cross section, the shape-elastic angular 2043 1451 113 distribution, the wave functions for the direct reaction cross 2043 1451 114 sections (see below), the transmission coefficients for the 2043 1451 115 compound nucleus model (see below) and the reaction cross 2043 1451 116 sections for the pre-equilibrium model (see below). 2043 1451 117 For neutrons and protons, the used parameterization is given in 2043 1451 118 Eq. (7) of [kon03]. 2043 1451 119 To calculate the transmission coefficients and reaction cross 2043 1451 120 sections for deuterons, tritons, helions and alpha particles, we 2043 1451 121 use OMPs that are directly derived from our nucleon potentials 2043 1451 122 using Watanabe's folding approach [mad88]. 2043 1451 123 2043 1451 124 ##### DIRECT REACTIONS 2043 1451 125 2043 1451 126 The built-in ECIS-97 is used for coupled-channels or DWBA 2043 1451 127 calculations for rotational or vibrational (or a combination of 2043 1451 128 these) nuclides. For Ca-46, DWBA was used to compute the direct 2043 1451 129 cross sections to several low-lying discrete levels: 2043 1451 130 2043 1451 131 Level Energy Spin/Parity Deformation parameter beta_l 2043 1451 132 2043 1451 133 1 1.346000 2.0+ 0.153 2043 1451 134 6 3.614000 3.0- 0.204 2043 1451 135 + a few additional states with small deformation parameters. 2043 1451 136 2043 1451 137 In addition, a macroscopic, phenomenological model to describe 2043 1451 138 giant resonances in the inelastic channel is used. For each 2043 1451 139 multipolarity an energy weighted sum rule applies and a DWBA 2043 1451 140 calculation with ECIS-97 is performed for each giant resonance 2043 1451 141 state. The cross section is then spread over the continuum with a 2043 1451 142 Gaussian distribution. 2043 1451 143 2043 1451 144 ##### COMPOUND NUCLEUS 2043 1451 145 2043 1451 146 For binary compound nucleus reactions we use the model of 2043 1451 147 Moldauer [mol80], i.e. the Hauser-Feshbach model [hau52] 2043 1451 148 corrected for width fluctuations. The transmission coefficients 2043 1451 149 have been generated with the aforementioned OMPs and the full 2043 1451 150 j,l-dependence of the transmission coefficients in the 2043 1451 151 Hauser-Feshbach model is used. For each nucleus that can be 2043 1451 152 reached through a binary reaction, several discrete levels and a 2043 1451 153 continuum described by level densities are included 2043 1451 154 simultaneously as competing channels. 2043 1451 155 2043 1451 156 The compound nucleus angular distributions are calculated with 2043 1451 157 the Blatt-Biedenharn formalism [bla52], leading to compound 2043 1451 158 nucleus Legendre coefficients that are added to their direct 2043 1451 159 counterparts. For multiple compound emission, i.e. emitted 2043 1451 160 particles after the binary emission, we use the Hauser-Feshbach 2043 1451 161 model. Again, for each residual nucleus several discrete states 2043 1451 162 are included as well as a continuum described by level densities. 2043 1451 163 Multiple compound emission is continued until all reaction 2043 1451 164 channels are closed and the population distribution of all 2043 1451 165 residual nuclides is depleted, through gamma decay, until they 2043 1451 166 end up in the ground state or in an isomer. 2043 1451 167 2043 1451 168 For the level density, we take the composite formula proposed by 2043 1451 169 Gilbert and Cameron [gil65], consisting of a constant temperature 2043 1451 170 law at low energies and a Fermi gas expression at high energies. 2043 1451 171 For the level density parameter a we use the energy dependent 2043 1451 172 expression proposed by Ignatyuk [ign75] to take into account the 2043 1451 173 damping of shell effects at high excitation energy. We have 2043 1451 174 obtained the parameters for the Ignatyuk formula from a 2043 1451 175 simultaneous fit to all experimental D_0 values as present in the 2043 1451 176 RIPL library. If necessary, we adjust individual parameters to 2043 1451 177 obtain a better fit to experiment. 2043 1451 178 2043 1451 179 Gamma-ray transmission coefficients are generated with the 2043 1451 180 Kopecky-Uhl generalized Lorentzian for strength 2043 1451 181 functions [kop90], with giant dipole resonance parameters taken 2043 1451 182 from the RIPL library [rip98], and normalized with experimental 2043 1451 183 radiative widths [gar84]. 2043 1451 184 2043 1451 185 ##### PRE-EQUILIBRIUM REACTIONS 2043 1451 186 2043 1451 187 For pre-equilibrium reactions, which become important for 2043 1451 188 incident energies above about 10 MeV, we use the two-component 2043 1451 189 exciton model [kon04b], in which the neutron or proton types of 2043 1451 190 particles and holes are followed throughout the reaction. For 2043 1451 191 energies above 20 MeV, multiple pre-equilibrium emission up to 2043 1451 192 any order of particle emission was included in the calculations. 2043 1451 193 A parameterization for the squared matrix element is used that is 2043 1451 194 valid for the whole energy range of this evaluation. 2043 1451 195 2043 1451 196 For deuterons, tritons, helions and alpha-particles, an extra 2043 1451 197 contribution was added from the pick/up and knock-out reaction 2043 1451 198 model by Kalbach [kal01]. 2043 1451 199 2043 1451 200 For photons, the model of Akkermans and Gruppelaar [akk85] was 2043 1451 201 applied, to simulate the direct and semi-direct capture 2043 1451 202 processes. 2043 1451 203 2043 1451 204 The angular distribution systematics by Kalbach [kal88] were used 2043 1451 205 to describe the angular distributions for all continuum 2043 1451 206 particles. An isotopic distribution for photons was adopted. 2043 1451 207 2043 1451 208 ****** C O M P A R I S O N W I T H E X P E R I M E N T *****2043 1451 209 2043 1451 210 This evaluation was performed simultaneously with other adjacent 2043 1451 211 isotopes, both for incident neutrons and protons. This enables, 2043 1451 212 when compared with a single-isotope effort, to put stronger 2043 1451 213 constraints on the produced calculated data, i.e. a globally 2043 1451 214 good comparison between TALYS and experimental data is requested 2043 1451 215 for all isotopes at the same time, while nucleus-specific input 2043 1451 216 (default or adjusted) parameters are consistently used for all 2043 1451 217 isotopes. Also, experimental data that is not available for the 2043 1451 218 isotope under study may be present, and tested, for adjacent 2043 1451 219 nuclides or for other projectiles. If these can be successfully 2043 1451 220 described by the models, a similar performance can be expected 2043 1451 221 for the present data file. 2043 1451 222 A few level density parameters for residual nuclides have been 2043 1451 223 adjusted to enforce agreement with the experimental data. The 2043 1451 224 changes in the level density parameters, a, were all kept within 2043 1451 225 10% of their default values. 2043 1451 226 2043 1451 227 ##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING 2043 1451 228 2043 1451 229 The spherical OMP was tested against experimental data for total 2043 1451 230 cross sections and elastic scattering angular distributions. 2043 1451 231 Consult [kon03] for the complete experimental database and for a 2043 1451 232 comparison of calculations and measurements over the whole energy 2043 1451 233 range for natural Ca. 2043 1451 234 2043 1451 235 ##### OTHER PARTIAL CROSS SECTIONS 2043 1451 236 2043 1451 237 - (n,gamma): 2043 1451 238 2043 1451 239 At thermal energy, the experimental value of 0.7 barn was used. 2043 1451 240 2043 1451 241 No other experimental data available. 2043 1451 242 2043 1451 243 ##### PARTICLE SPECTRA 2043 1451 244 2043 1451 245 For Ca-46, an adjustment of the default matrix element 2043 1451 246 parameterization of [kon04b] for pre-equilibrium reactions of a 2043 1451 247 factor of 0.7 was needed, to describe the emission spectra for 2043 1451 248 nuclides in this mass range. 2043 1451 249 For high-energy neutron and charged particle spectra, the average 2043 1451 250 quality is also determined by the pre-equilibrium model and its 2043 1451 251 global parameterization. No high-energy experiments are 2043 1451 252 available, though neutron induced reaction spectra between 28 and 2043 1451 253 63 MeV on Al [ben02], Si [ben02b] and Fe [sly03] have enabled us 2043 1451 254 to better constrain the results, through the aforementioned 2043 1451 255 matrix element, for particle yields and double-differential 2043 1451 256 spectra for all ejectiles up to alpha particles. 2043 1451 257 2043 1451 258 ***************** F I L E I N F O R M A T I O N ****************2043 1451 259 2043 1451 260 ##### MF1: GENERAL INFORMATION 2043 1451 261 2043 1451 262 - MT451 : Descriptive data and directory 2043 1451 263 2043 1451 264 This text and the full directory of used MF/MT sections. 2043 1451 265 2043 1451 266 ##### MF2: RESONANCE PARAMETERS 2043 1451 267 2043 1451 268 - MT151 : Resonance parameters 2043 1451 269 2043 1451 270 No resonance parameters available. 2043 1451 271 2043 1451 272 ##### MF3: REACTION CROSS SECTIONS 2043 1451 273 2043 1451 274 Unless stated otherwise, all the data present in the following 2043 1451 275 MT-sections have been calculated with TALYS. If the maximal cross 2043 1451 276 section in an excitation function over the whole energy range 2043 1451 277 does not exceed 1.e-9 b, the MT-number is not included at all. 2043 1451 278 Cross sections lower than 1.e-20 b are assumed to have no 2043 1451 279 physical meaning and are set to zero. 2043 1451 280 2043 1451 281 - MT1 : Total cross section 2043 1451 282 2043 1451 283 Calculations from the spherical OMP [kon03] were used. 2043 1451 284 2043 1451 285 - MT2 : Elastic scattering cross section 2043 1451 286 2043 1451 287 Obtained by subtracting the non-elastic cross section from the 2043 1451 288 total cross section. 2043 1451 289 2043 1451 290 - MT3 : Non-elastic cross section 2043 1451 291 2043 1451 292 Calculated with the optical model over the whole energy range. 2043 1451 293 2043 1451 294 - MT4 : Total inelastic cross section 2043 1451 295 2043 1451 296 Sum of MT=51-91. 2043 1451 297 2043 1451 298 - MT5 : (n,anything) cross section 2043 1451 299 2043 1451 300 For energies below 20 MeV, MT5 contains the lumped (n,gamma x) 2043 1451 301 cross section, where x may represent neutron, proton, deuteron, 2043 1451 302 triton, Helium-3 or alpha. Using the relative yields of MF6/MT5, 2043 1451 303 the (n,gamma n), (n,gamma p), ..., (n,gamma alpha) can be 2043 1451 304 recovered. These cross sections are relatively small. However, 2043 1451 305 addition of these cross sections, which can not be stored in any 2043 1451 306 other MT-number, ensures that the partial cross sections add up 2043 1451 307 to the non-elastic cross section. Above 20 MeV, MT5 contains the 2043 1451 308 total non-elastic cross section, with which the information of 2043 1451 309 MF6/MT5 can be combined to obtain particle production cross 2043 1451 310 sections and (double-)differential cross sections. 2043 1451 311 2043 1451 312 - MT16 : (n,2n) cross section 2043 1451 313 - MT17 : (n,3n) cross section 2043 1451 314 - MT22 : (n,na) cross section 2043 1451 315 - MT28 : (n,np) cross section 2043 1451 316 - MT51-70 : (n,n') cross section for 1st-20th excited state 2043 1451 317 - MT91 : (n,n') continuum cross section 2043 1451 318 - MT102 : (n,gamma) cross section 2043 1451 319 - MT103 : (n,p) cross section 2043 1451 320 - MT104 : (n,d) cross section 2043 1451 321 - MT105 : (n,t) cross section 2043 1451 322 - MT107 : (n,a) cross section 2043 1451 323 - MT600-610: (n,p) cross section for 0th-10th excited state 2043 1451 324 2043 1451 325 Obtained by mapping continuum (n,p) cross section from 2043 1451 326 pre-equilibrium and compound model on discrete states. 2043 1451 327 2043 1451 328 - MT649 : (n,p) continuum cross section 2043 1451 329 - MT650-655: (n,d) cross section for 0th-5th excited state 2043 1451 330 2043 1451 331 Obtained by mapping continuum (n,d) cross section from 2043 1451 332 pre-equilibrium and compound model on discrete states. 2043 1451 333 2043 1451 334 - MT699 : (n,d) continuum cross section 2043 1451 335 - MT700-705: (n,t) cross section for 0th-5th excited state 2043 1451 336 2043 1451 337 Obtained by mapping continuum (n,t) cross section from 2043 1451 338 pre-equilibrium and compound model on discrete states. 2043 1451 339 2043 1451 340 - MT749 : (n,t) continuum cross section 2043 1451 341 - MT800-804: (n,a) cross section for 0th-4th excited state 2043 1451 342 2043 1451 343 Obtained by mapping continuum (n,a) cross section from 2043 1451 344 pre-equilibrium and compound model on discrete states. 2043 1451 345 2043 1451 346 - MT849 : (n,a) continuum cross section 2043 1451 347 2043 1451 348 ##### MF4: ANGULAR DISTRIBUTIONS OF SECONDARY PARTICLES 2043 1451 349 2043 1451 350 The versatility of MF6 for the storage of almost any secondary 2043 1451 351 distribution entails that we only use MF4 for the neutron elastic 2043 1451 352 scattering distribution. All data are generated with TALYS. 2043 1451 353 2043 1451 354 - MT2 : Elastic angular distribution 2043 1451 355 2043 1451 356 The flag LTT=3 is used to indicate a switch at 20 MeV from a 2043 1451 357 Legendre representation to a tabulated representation. For 2043 1451 358 incident energies below 20 MeV, the Legendre coefficients are 2043 1451 359 given on a sufficiently precise energy grid. They are a sum of 2043 1451 360 calculated Legendre coefficients for compound nucleus and 2043 1451 361 shape-elastic scattering. For incident energies above 20 MeV, 2043 1451 362 relative angular distributions are tabulated on an angular grid. 2043 1451 363 2043 1451 364 ##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS 2043 1451 365 2043 1451 366 In MF6 we store all secondary energy, angle, and energy-angle 2043 1451 367 distributions, as well as all residual and discrete + continuum 2043 1451 368 photon production cross sections. We thus do not use MF12-15 for 2043 1451 369 the photon production that accompanies each reaction. All data 2043 1451 370 are generated with TALYS. 2043 1451 371 2043 1451 372 - MT5 : (n,anything) yields and energy-angle distributions 2043 1451 373 2043 1451 374 For energies below 20 MeV, MT5 contains the relative yields of 2043 1451 375 the (n,gamma x) reaction, where x may represent neutron, proton, 2043 1451 376 deuteron, triton, Helium-3 or alpha. Using the (n,gamma x) cross 2043 1451 377 section of MF3/MT3, the (n,gamma p), ..., (n,gamma alpha) cross 2043 1451 378 section can be recovered. For energies above 20 MeV, MT5 contains 2043 1451 379 the production yields of particles and residual products. It also 2043 1451 380 contains the secondary energy-angle distributions for all 2043 1451 381 particles and photons. First, the yields for neutrons are given 2043 1451 382 for the whole energy range. Next, on a secondary energy grid the 2043 1451 383 relative emission spectra are given together with the parameters 2043 1451 384 for the Kalbach systematics for angular distributions. Inelastic 2043 1451 385 scattering cross sections for discrete states have been broadened 2043 1451 386 and added to the continuum spectra. This procedure is repeated 2043 1451 387 for protons, deuterons, tritons, Helium-3, alpha particles and 2043 1451 388 photons. Finally, the residual production yields are given per 2043 1451 389 final product. All these yields and relative distributions can 2043 1451 390 be multiplied with the cross sections given in MF3/MT5 to get 2043 1451 391 the production cross sections and (double-)differential cross 2043 1451 392 sections. 2043 1451 393 2043 1451 394 - MT16 : (n,2n) energy-angle distr. and photon production 2043 1451 395 2043 1451 396 First, for each type of outgoing particle, the (trivial) integer 2043 1451 397 particle yields are given. Next, on a sufficiently dense incident 2043 1451 398 energy grid the secondary energy-angle distributions are 2043 1451 399 specified by means of the relative emission spectra and the 2043 1451 400 parameters for the Kalbach systematics for angular distributions. 2043 1451 401 Next, the photon yield is tabulated as a function of incident 2043 1451 402 energy. For each incident energy, the photon production is given 2043 1451 403 for all discrete gamma lines present in the final nucleus. A 2043 1451 404 continuum photon distribution is added to this. We assume 2043 1451 405 isotropy for all produced gamma rays. 2043 1451 406 2043 1451 407 For the following MT-numbers, the same procedure as for MT16 is 2043 1451 408 followed: 2043 1451 409 ----- 2043 1451 410 - MT17 : (n,3n) energy-angle distr. and photon production 2043 1451 411 - MT22 : (n,na) energy-angle distr. and photon production 2043 1451 412 - MT28 : (n,np) energy-angle distr. and photon production 2043 1451 413 - MT91 : (n,n') continuum energy-angle distr. and phot. prod. 2043 1451 414 - MT102 : (n,gamma) photon production 2043 1451 415 - MT649 : (n,p) continuum energy-angle distr. and photon prod. 2043 1451 416 - MT699 : (n,d) continuum energy-angle distr. and photon prod. 2043 1451 417 - MT749 : (n,t) continuum energy-angle distr. and photon prod. 2043 1451 418 - MT849 : (n,a) continuum energy-angle distr. and photon prod. 2043 1451 419 ----- 2043 1451 420 2043 1451 421 - MT51 : (n,n') angular distribution and photon production 2043 1451 422 for first excited state 2043 1451 423 2043 1451 424 The angular distribution for inelastic scattering to the first 2043 1451 425 inelastic state is given with Legendre coefficients up to 20 MeV. 2043 1451 426 Next, the exclusive yields for all the discrete gamma rays that 2043 1451 427 originate from this particular level are given. 2043 1451 428 2043 1451 429 For the following MT-numbers, the same procedure as for MT51 is 2043 1451 430 followed: 2043 1451 431 ----- 2043 1451 432 - MT52-70 : (n,n') angular distribution and photon production 2043 1451 433 for 2nd-20th excited state 2043 1451 434 - MT600-610: (n,p) angular distribution and photon production 2043 1451 435 for 0th-10th excited state 2043 1451 436 - MT650-655: (n,d) angular distribution and photon production 2043 1451 437 for 0th-5th excited state 2043 1451 438 - MT700-705: (n,t) angular distribution and photon production 2043 1451 439 for 0th-5th excited state 2043 1451 440 - MT800-810: (n,a) angular distribution and photon production 2043 1451 441 for 0th-10th excited state 2043 1451 442 ----- 2043 1451 443 2043 1451 444 ***** F I L E C H E C K I N G A N D P R O C E S S I N G ****2043 1451 445 2043 1451 446 This file has been checked successfully by the BNL checking 2043 1451 447 codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has 2043 1451 448 been processed successfully into an MCNP library by the 2043 1451 449 processing code NJOY99.81 [mac00]. 2043 1451 450 2043 1451 451 *********************** R E F E R E N C E S **********************2043 1451 452 2043 1451 453 [akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95 2043 1451 454 (1985). 2043 1451 455 [ben02] S. Benck, I. Slypen, J.-P. Meulders, V. Corcalciuc, and 2043 1451 456 M.B. Chadwick, Nucl. Sci. Eng. 140, 86 (2002). 2043 1451 457 [ben02b] S. Benck, I. Slypen, J.-P. Meulders, and V. Corcalciuc, 2043 1451 458 Nucl. Sci. Eng. 141, 1 (2002). 2043 1451 459 [ber03] O. Bersillon, Bruyeres-le-Chatel, private communication. 2043 1451 460 [bla52] J.M. Blatt and L.C. Biedenharn, Rev. Mod. Phys. 52, 725 2043 1451 461 (1952). 2043 1451 462 [dun01] C. Dunford, ENDF Utility Codes Release 6.12, (2001). 2043 1451 463 [gar84] D.G. Gardner, in Neutron Radiative Capture, OECD/NEA 2043 1451 464 Series on Neutron Physics and Nuclear Data in Science and 2043 1451 465 Technology, eds. A. Michaudon et al., p. 62 (1984). 2043 1451 466 [gil65] A. Gilbert and A.G.W. Cameron, Can. J. Phys. 43, 1446 2043 1451 467 (1965). 2043 1451 468 [hau52] W. Hauser and H. Feshbach, Phys. Rev. 87, 366 (1952). 2043 1451 469 [ign75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov. J. 2043 1451 470 Nucl. Phys. 21, no. 3, 255 (1975). 2043 1451 471 [kal88] C. Kalbach, Phys. Rev. C37, 2350 (1988). 2043 1451 472 [kal01] C. Kalbach, PRECO-2000: Exciton model pre-equilibrium 2043 1451 473 code with direct reactions, Duke University 2001, 2043 1451 474 www.nndc.bnl.gov/nndcscr/model-codes/preco-2000/. 2043 1451 475 [kon03] A.J. Koning and J.P. Delaroche, Nucl. Phys. A713, 231 2043 1451 476 (2003). 2043 1451 477 [kon04] A.J. Koning, S. Hilaire and M.C. Duijvestijn, unpublished 2043 1451 478 (2004). 2043 1451 479 [kon04b] A.J. Koning and M.C. Duijvestijn, to be published 2043 1451 480 (2004). 2043 1451 481 [kop90] J. Kopecky and M. Uhl, Phys. Rev. C42, 1941 (1990). 2043 1451 482 [mac00] R.E. Macfarlane, NJOY99 - Code system for producing 2043 1451 483 pointwise and multigroup neutron and photon cross 2043 1451 484 sections from ENDF/B Data, RSIC PSR-480 (2000). 2043 1451 485 [mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on 2043 1451 486 Preequilibrium Reactions, Semmering, Austria, 2043 1451 487 February 10-12 1988, (OECD, Paris 1988), p. 103. 2043 1451 488 [mol80] P.A. Moldauer, Nucl. Phys. A344, 185 (1980). 2043 1451 489 [mug81] S.F. Mughabghab, M. Divadeenam, and. N.E. Holden, 2043 1451 490 Neutron Cross Sections, Vol. I, Neutron Resonance 2043 1451 491 Parameters and Thermal Cross Sections (Academic Press, 2043 1451 492 1981). 2043 1451 493 [ray94] J. Raynal, Notes on ECIS94, CEA Saclay Report 2043 1451 494 No. CEA-N-2772, 1994. 2043 1451 495 [rip98] Handbook for calculations of nuclear reaction data: 2043 1451 496 Reference Input Parameter Library, IAEA-TECDOC-1034 2043 1451 497 (1998). 2043 1451 498 [sly03] I. Slypen, N. Nica, A.J. Koning, E. Raeymackers, 2043 1451 499 S. Benck, J.P. Meulders, and V. Corcalciuc, 2043 1451 500 Journ. Phys. G, November 2003 (2003). 2043 1451 501 2043 1451 502 ************************* C O N T E N T S ************************2043 1451 503 2043 1451 504 1 451 633 12043 1451 505 2 151 4 12043 1451 506 3 1 116 12043 1451 507 3 2 103 12043 1451 508 3 3 104 12043 1451 509 3 4 28 12043 1451 510 3 5 70 12043 1451 511 3 16 9 12043 1451 512 3 17 5 12043 1451 513 3 22 8 12043 1451 514 3 28 7 12043 1451 515 3 51 28 12043 1451 516 3 52 26 12043 1451 517 3 53 25 12043 1451 518 3 54 24 12043 1451 519 3 55 24 12043 1451 520 3 56 23 12043 1451 521 3 57 22 12043 1451 522 3 58 22 12043 1451 523 3 59 21 12043 1451 524 3 60 21 12043 1451 525 3 61 20 12043 1451 526 3 62 20 12043 1451 527 3 63 19 12043 1451 528 3 64 19 12043 1451 529 3 65 18 12043 1451 530 3 66 17 12043 1451 531 3 67 17 12043 1451 532 3 68 17 12043 1451 533 3 69 16 12043 1451 534 3 70 16 12043 1451 535 3 91 16 12043 1451 536 3 102 29 12043 1451 537 3 103 16 12043 1451 538 3 104 10 12043 1451 539 3 105 8 12043 1451 540 3 107 15 12043 1451 541 3 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