832090 JEFF 3.1 library 2310 0 0 0 8.320900+4 2.071852+2 1 0 2 18325 1451 1 0.000000+0 0.000000+0 0 0 0 68325 1451 2 1.000000+0 2.000000+8 1 0 10 318325 1451 3 0.000000+0 0.000000+0 0 0 665 1708325 1451 4 83-Bi-209 NRG EVAL-DEC04 A.J. Koning 8325 1451 5 NRG-2004 DIST-MAY05 REV1-MAY05 20050504 8325 1451 6 ----JEFF-31 Material 8325 REVISION 1 8325 1451 7 -----Incident neutron data 8325 1451 8 ------ENDF-6 Format 8325 1451 9 ***************************** JEFF-3.1 *************************8325 1451 10 ** **8325 1451 11 ** Original data taken from: New evaluation **8325 1451 12 ** **8325 1451 13 ******************************************************************8325 1451 14 8325 1451 15 NRG-2004: n + Bi-209 8325 1451 16 8325 1451 17 Author: A.J. Koning, NRG Petten 8325 1451 18 8325 1451 19 ************** G E N E R A L I N F O R M A T I O N *************8325 1451 20 8325 1451 21 This evaluated data file is based primarily on a theoretical 8325 1451 22 analysis with the nuclear model code TALYS [kon04], version 0.56. 8325 1451 23 The nuclear model parameters of TALYS have been adjusted to 8325 1451 24 reproduce the existing experimental data. The resulting data file 8325 1451 25 provides a complete representation of nuclear data needed for 8325 1451 26 transport, damage, heating, radioactivity, and shielding 8325 1451 27 applications over the incident neutron energy range from 8325 1451 28 1.0E-11 to 200 MeV. 8325 1451 29 8325 1451 30 This file is part of a larger collection of isotopic evaluations, 8325 1451 31 all created by running TALYS with input parameters that do not or 8325 1451 32 slightly deviate from the default values. The mutual quality of 8325 1451 33 these isotopic evaluations is thus relatively consistent. 8325 1451 34 The same set of nuclear models is used and, equally important, 8325 1451 35 the same ENDF-6 formatting procedures for each isotope. We have 8325 1451 36 intended to make this evaluation complete in its description of 8325 1451 37 reaction channels, and use a compact method to store the data. 8325 1451 38 8325 1451 39 For certain reactions and energy ranges TALYS may not be used. 8325 1451 40 This is the case when TALYS is not appropriate, such as for the 8325 1451 41 description of resonances, or when the directly available 8325 1451 42 experimental data is of better quality, as for e.g. low-energy 8325 1451 43 total cross sections. In these cases, we have adopted the best 8325 1451 44 possible data from an existing library, or directly from unfiled 8325 1451 45 experimental data. All transport data for particles, photons and 8325 1451 46 residual nuclides are filed using a combination of MF1,2,3,4 and 8325 1451 47 MF6. This includes cross sections, angular distributions, 8325 1451 48 double-differential spectra, discrete and continuum photon 8325 1451 49 production cross sections, and residual production (activation) 8325 1451 50 cross sections. Moreover, isomeric production data are stored in 8325 1451 51 MF8 and MF10. This evaluation can thus be used as both transport 8325 1451 52 and activation library. The data file has been created 8325 1451 53 automatically using the ENDF-6 format generator TEFAL. 8325 1451 54 8325 1451 55 ##### ORIGIN 8325 1451 56 8325 1451 57 Data < 200 MeV : New evaluation NRG Petten 8325 1451 58 8325 1451 59 Resonance parameters (MF2/MT151): JENDL-3.3 for E < 200 keV 8325 1451 60 Total cross sections (MF3/MT1) : ENDF/B-VI.8 for E < 6.5 MeV 8325 1451 61 All other data : Produced with TALYS code 8325 1451 62 8325 1451 63 *************************** T H E O R Y **************************8325 1451 64 8325 1451 65 TALYS is a computer code system for the prediction and analysis 8325 1451 66 of nuclear reactions. TALYS simulates reactions that involve 8325 1451 67 neutrons, gamma-rays, protons, deuterons, tritons, helions and 8325 1451 68 alpha-particles, in the 1 keV - 200 MeV energy range and for 8325 1451 69 target nuclides of mass 12 and heavier. This is achieved by 8325 1451 70 implementing a suite of nuclear reaction models into a single 8325 1451 71 code system. It enables to evaluate nuclear reactions from 8325 1451 72 the unresolved resonance region up to intermediate energies. This 8325 1451 73 evaluation is based on a theoretical analysis that utilizes the 8325 1451 74 optical model, compound nucleus statistical theory, direct 8325 1451 75 reactions and pre-equilibrium processes, in combination with 8325 1451 76 databases and models for nuclear structure. For Bi-209, the 8325 1451 77 following output of TALYS is stored in this data file: 8325 1451 78 8325 1451 79 - Total, elastic and non-elastic cross sections 8325 1451 80 - Elastic scattering angular distributions 8325 1451 81 - Inelastic cross sections to discrete states 8325 1451 82 - Inelastic scattering angular distributions to discrete states 8325 1451 83 - Exclusive channel cross sections, e.g. (n,g), (n,2n), (n,np),.. 8325 1451 84 - Exclusive channel energy spectra 8325 1451 85 - Exclusive channel double-differential spectra 8325 1451 86 - Exclusive gamma production for discrete states and continuum 8325 1451 87 - Isomeric and ground state cross sections 8325 1451 88 - Residual production cross sections 8325 1451 89 - Total particle cross sections, e.g. (n,xn), (n,xp),.. 8325 1451 90 - Total particle energy spectra 8325 1451 91 - Total particle double-differential spectra 8325 1451 92 8325 1451 93 Here follows a short description of the used nuclear models: 8325 1451 94 8325 1451 95 ##### OPTICAL MODEL 8325 1451 96 8325 1451 97 All optical model calculations are performed by ECIS-97 [ray94], 8325 1451 98 in TALYS used as a subroutine. The default optical model 8325 1451 99 potentials (OMP) used are the local and global parameterizations 8325 1451 100 of Koning and Delaroche [kon03]. These are phenomenological OMPs 8325 1451 101 for neutrons and protons which in principle are valid over the 8325 1451 102 1 keV - 200 MeV energy range, though the low energy boundary of 8325 1451 103 validity may differ from nucleus to nucleus (e.g. for the total 8325 1451 104 cross sections, experimental data are included directly in the 8325 1451 105 file for energies below that boundary). Solving the Schroedinger 8325 1451 106 equation with this OMP yields the total cross section, the 8325 1451 107 shape-elastic cross section, the shape-elastic angular 8325 1451 108 distribution, the wave functions for the direct reaction cross 8325 1451 109 sections (see below), the transmission coefficients for the 8325 1451 110 compound nucleus model (see below) and the reaction cross 8325 1451 111 sections for the pre-equilibrium model (see below). 8325 1451 112 For neutrons and protons, the used parameterization is given in 8325 1451 113 Eq. (7) of [kon03]. 8325 1451 114 To calculate the transmission coefficients and reaction cross 8325 1451 115 sections for deuterons, tritons, helions and alpha particles, we 8325 1451 116 use OMPs that are directly derived from our nucleon potentials 8325 1451 117 using Watanabe's folding approach [mad88]. 8325 1451 118 8325 1451 119 ##### DIRECT REACTIONS 8325 1451 120 8325 1451 121 The built-in ECIS-97 is used for coupled-channels or DWBA 8325 1451 122 calculations for rotational or vibrational (or a combination of 8325 1451 123 these) nuclides. For Bi-209, DWBA was used to compute the direct 8325 1451 124 cross sections to several low-lying discrete levels of the 8325 1451 125 even-even core Pb-208. The weak-coupling model was then used 8325 1451 126 to spread the collective strength over the odd levels of Bi-209. 8325 1451 127 8325 1451 128 In addition, a macroscopic, phenomenological model to describe 8325 1451 129 giant resonances in the inelastic channel is used. For each 8325 1451 130 multipolarity an energy weighted sum rule applies and a DWBA 8325 1451 131 calculation with ECIS-97 is performed for each giant resonance 8325 1451 132 state. The cross section is then spread over the continuum with a 8325 1451 133 Gaussian distribution. 8325 1451 134 8325 1451 135 ##### COMPOUND NUCLEUS 8325 1451 136 8325 1451 137 For binary compound nucleus reactions we use the model of 8325 1451 138 Moldauer [mol80], i.e. the Hauser-Feshbach model [hau52] 8325 1451 139 corrected for width fluctuations. The transmission coefficients 8325 1451 140 have been generated with the aforementioned OMPs and the full 8325 1451 141 j,l-dependence of the transmission coefficients in the 8325 1451 142 Hauser-Feshbach model is used. For each nucleus that can be 8325 1451 143 reached through a binary reaction, several discrete levels and a 8325 1451 144 continuum described by level densities are included 8325 1451 145 simultaneously as competing channels. 8325 1451 146 8325 1451 147 The compound nucleus angular distributions are calculated with 8325 1451 148 the Blatt-Biedenharn formalism [bla52], leading to compound 8325 1451 149 nucleus Legendre coefficients that are added to their direct 8325 1451 150 counterparts. For multiple compound emission, i.e. emitted 8325 1451 151 particles after the binary emission, we use the Hauser-Feshbach 8325 1451 152 model. Again, for each residual nucleus several discrete states 8325 1451 153 are included as well as a continuum described by level densities. 8325 1451 154 Multiple compound emission is continued until all reaction 8325 1451 155 channels are closed and the population distribution of all 8325 1451 156 residual nuclides is depleted, through gamma decay, until they 8325 1451 157 end up in the ground state or in an isomer. 8325 1451 158 8325 1451 159 For the level density, we take the composite formula proposed by 8325 1451 160 Gilbert and Cameron [gil65], consisting of a constant temperature 8325 1451 161 law at low energies and a Fermi gas expression at high energies. 8325 1451 162 For the level density parameter a we use the energy dependent 8325 1451 163 expression proposed by Ignatyuk [ign75] to take into account the 8325 1451 164 damping of shell effects at high excitation energy. We have 8325 1451 165 obtained the parameters for the Ignatyuk formula from a 8325 1451 166 simultaneous fit to all experimental D_0 values as present in the 8325 1451 167 RIPL library. If necessary, we adjust individual parameters to 8325 1451 168 obtain a better fit to experiment. 8325 1451 169 8325 1451 170 Gamma-ray transmission coefficients are generated with the 8325 1451 171 Kopecky-Uhl generalized Lorentzian for strength 8325 1451 172 functions [kop90], with giant dipole resonance parameters taken 8325 1451 173 from the RIPL library [rip98], and normalized with experimental 8325 1451 174 radiative widths [gar84]. 8325 1451 175 8325 1451 176 ##### PRE-EQUILIBRIUM REACTIONS 8325 1451 177 8325 1451 178 For pre-equilibrium reactions, which become important for 8325 1451 179 incident energies above about 10 MeV, we use the two-component 8325 1451 180 exciton model [kon04b], in which the neutron or proton types of 8325 1451 181 particles and holes are followed throughout the reaction. For 8325 1451 182 energies above 20 MeV, multiple pre-equilibrium emission up to 8325 1451 183 any order of particle emission was included in the calculations. 8325 1451 184 A parameterization for the squared matrix element is used that is 8325 1451 185 valid for the whole energy range of this evaluation. 8325 1451 186 8325 1451 187 For deuterons, tritons, helions and alpha-particles, an extra 8325 1451 188 contribution was added from the pick/up and knock-out reaction 8325 1451 189 model by Kalbach [kal01]. 8325 1451 190 8325 1451 191 For photons, the model of Akkermans and Gruppelaar [akk85] was 8325 1451 192 applied, to simulate the direct and semi-direct capture 8325 1451 193 processes. 8325 1451 194 8325 1451 195 The angular distribution systematics by Kalbach [kal88] were used 8325 1451 196 to describe the angular distributions for all continuum 8325 1451 197 particles. An isotopic distribution for photons was adopted. 8325 1451 198 8325 1451 199 ****** C O M P A R I S O N W I T H E X P E R I M E N T *****8325 1451 200 8325 1451 201 This evaluation was performed simultaneously with other adjacent 8325 1451 202 isotopes, both for incident neutrons and protons. This enables, 8325 1451 203 when compared with a single-isotope effort, to put stronger 8325 1451 204 constraints on the produced calculated data, i.e. a globally 8325 1451 205 good comparison between TALYS and experimental data is requested 8325 1451 206 for all isotopes at the same time, while nucleus-specific input 8325 1451 207 (default or adjusted) parameters are consistently used for all 8325 1451 208 isotopes. Also, experimental data that is not available for the 8325 1451 209 isotope under study may be present, and tested, for adjacent 8325 1451 210 nuclides or for other projectiles. If these can be successfully 8325 1451 211 described by the models, a similar performance can be expected 8325 1451 212 for the present data file. Examples are the (p,xn)....(p,xa) 8325 1451 213 spectra for Pb-208 and Pb-nat and the (n,xng) data for Pb-208. 8325 1451 214 8325 1451 215 ##### TOTAL AND REACTION CROSS SECTIONS AND ELASTIC SCATTERING 8325 1451 216 8325 1451 217 The spherical OMP was tested against experimental data for 8325 1451 218 Bi-209, in particular the cross section set of [fin93]. 8325 1451 219 For inelastic scattering, it turns out that our local OMP for 8325 1451 220 Bi-209 needs a slight change in the parameterization, as compared 8325 1451 221 to the parameters given in [kon03]. Also the total cross section 8325 1451 222 at high energies could be slightly improved. The used parameters 8325 1451 223 are those of Tables 5-6 of [kon03], with the following changes: 8325 1451 224 8325 1451 225 v1: 50.1 --> 49.3 MeV 8325 1451 226 v2: 0.0069 --> 0.067 /MeV 8325 1451 227 v3: 0.000015--> 0.000012 /(MeV**2) 8325 1451 228 w1: 15.4 --> 17.4 MeV 8325 1451 229 w2: 88 --> 96 MeV 8325 1451 230 rd: 1.255 --> 1.245 fm 8325 1451 231 d1: 13.8 --> 13.6 MeV 8325 1451 232 d3: 13.8 --> 11.8 MeV 8325 1451 233 vso1: 6.6 --> 6.9 MeV 8325 1451 234 vso2: 0.035 --> 0.015 /MeV 8325 1451 235 8325 1451 236 Consult [kon03] for the complete experimental database of elastic 8325 1451 237 scattering angular distributions and for a comparison of 8325 1451 238 calculations and measurements over the whole energy range. 8325 1451 239 8325 1451 240 ##### INELASTIC CROSS SECTIONS 8325 1451 241 8325 1451 242 For the total inelastic cross section, the calculated results 8325 1451 243 were compared with various experimental data sets 8325 1451 244 [tom63,owe68,joe69,pro80,shi82,sim92,las94]. The description is 8325 1451 245 good on average. For inelastic scattering to the first excited 8325 1451 246 state, the calculations have been tested against the available 8325 1451 247 measurements [smi70,gue80,alm75], where good agreement is 8325 1451 248 obtained with the data of the first two references. 8325 1451 249 For inelastic scattering to the second and the 3rd up to the 8325 1451 250 13th state, available in groups of levels, the calculations have 8325 1451 251 also been successfully tested against the data of [alm75,gue80]. 8325 1451 252 No further renormalization was necessary to describe the 8325 1451 253 experiments. 8325 1451 254 8325 1451 255 ##### OTHER PARTIAL CROSS SECTIONS 8325 1451 256 8325 1451 257 - (n,gamma): 8325 1451 258 8325 1451 259 The calculated capture cross section is renormalized, by 8325 1451 260 overruling the default renormalization to the s-wave strength 8325 1451 261 function, to the available experimental data, all taken from the 8325 1451 262 EXFOR database. A normalization factor of 1.45 was used. Further, 8325 1451 263 the E1 giant resonance energy was changed to 15.5 MeV, and its 8325 1451 264 strength to 750 mb, to better describe the direct/semi-direct 8325 1451 265 peak around an incident energy of 14 MeV. The pre-equilibrium 8325 1451 266 gamma cross section was adjusted to the data by multiplying the 8325 1451 267 calculated result by a factor of 1.5. 8325 1451 268 8325 1451 269 - (n,2n): 8325 1451 270 8325 1451 271 The calculated results have been validated with the experimental 8325 1451 272 (n,2n) cross section of Frehaut [fre80], taking into account a 8325 1451 273 necessary 10-15 % renormalization of the experimental data that 8325 1451 274 was recently reported [ber03], and the data of Veeser [vee77]. 8325 1451 275 8325 1451 276 - (n,3n): 8325 1451 277 8325 1451 278 Validated with experimental data of [vee77,pro80,kim98]. 8325 1451 279 8325 1451 280 - (n,4n)-(n,12n): 8325 1451 281 8325 1451 282 Measurements up to (n,12n) have been performed by Kim et al 8325 1451 283 [kim98]. TALYS gives a good average description of all these 8325 1451 284 reaction channels up to 150 MeV. 8325 1451 285 8325 1451 286 - (n,p): 8325 1451 287 8325 1451 288 Various near-threshold values are available from EXFOR. TALYS 8325 1451 289 slightly overestimates these values by 1 mb. No further 8325 1451 290 adjustment was done. 8325 1451 291 8325 1451 292 - (n,a): 8325 1451 293 8325 1451 294 Various near-threshold values are available from EXFOR. TALYS 8325 1451 295 slightly overestimates these values by a few mb. No further 8325 1451 296 adjustment was done. 8325 1451 297 8325 1451 298 ##### PARTICLE SPECTRA 8325 1451 299 8325 1451 300 For Bi-209, no adjustment of the default matrix element 8325 1451 301 parameterization of [kon04b] for pre-equilibrium reactions was 8325 1451 302 needed, to describe the aforementioned cross sections and 8325 1451 303 emission spectra at 14 [tak88], 20 [mar91] and 26 [mar83] MeV. 8325 1451 304 For high-energy neutron and charged particle spectra, the average 8325 1451 305 quality is also determined by the pre-equilibrium model and its 8325 1451 306 global parameterization. The experiment from Louvain-la-Neuve of 8325 1451 307 28-63 MeV (n,xp...xa) spectra on Bi-209, and two experiments from 8325 1451 308 the HINDAS project, for neutron induced reaction spectra at 63 8325 1451 309 MeV [ker02] and 96 MeV [lec03] on the adjacent Pb element, have 8325 1451 310 enabled us to better constrain the results, through the 8325 1451 311 aforementioned matrix element, for particle yields and 8325 1451 312 double-differential spectra for all ejectiles up to alpha 8325 1451 313 particles. 8325 1451 314 8325 1451 315 ***************** F I L E I N F O R M A T I O N ****************8325 1451 316 8325 1451 317 ##### MF1: GENERAL INFORMATION 8325 1451 318 8325 1451 319 - MT451 : Descriptive data and directory 8325 1451 320 8325 1451 321 This text and the full directory of used MF/MT sections. 8325 1451 322 8325 1451 323 ##### MF2: RESONANCE PARAMETERS 8325 1451 324 8325 1451 325 - MT151 : Resonance parameters 8325 1451 326 8325 1451 327 MLBW resolved resonance parameters covering the energy range 8325 1451 328 1.0e-5 eV to 200 keV were adopted from the JENDL-3.3 evaluation. 8325 1451 329 They are based on [mug81]. 8325 1451 330 Scattering radius: 9.68 fm 8325 1451 331 Calculated 2200-m/s cross sections and res. integrals 8325 1451 332 2200-m/s res. integ. 8325 1451 333 elastic 9.298 b - 8325 1451 334 capture 0.034 b 0.199 b 8325 1451 335 total 9.331 b - 8325 1451 336 8325 1451 337 ##### MF3: REACTION CROSS SECTIONS 8325 1451 338 8325 1451 339 Unless stated otherwise, all the data present in the following 8325 1451 340 MT-sections have been calculated with TALYS. If the maximal cross 8325 1451 341 section in an excitation function over the whole energy range 8325 1451 342 does not exceed 1.e-9 b, the MT-number is not included at all. 8325 1451 343 Cross sections lower than 1.e-20 b are assumed to have no 8325 1451 344 physical meaning and are set to zero. 8325 1451 345 8325 1451 346 - MT1 : Total cross section 8325 1451 347 8325 1451 348 Below 6.5 MeV, MT1 is adopted from ENDF/B-VI.8. The experimental 8325 1451 349 total cross sections from [smi70,fos71] are used above the 8325 1451 350 resonance range (> 200 keV). Above 6.5 MeV, calculations from the 8325 1451 351 spherical OMP were used. 8325 1451 352 8325 1451 353 - MT2 : Elastic scattering cross section 8325 1451 354 8325 1451 355 Obtained by subtracting the non-elastic cross section from the 8325 1451 356 total cross section. At energies below 6.5 MeV, the elastic 8325 1451 357 cross section is thus derived from evaluated experiment-based 8325 1451 358 total cross sections and optical model based non-elastic cross 8325 1451 359 sections. Below 200 keV, resonance parameters are used. 8325 1451 360 8325 1451 361 - MT3 : Non-elastic cross section 8325 1451 362 8325 1451 363 Calculated with the optical model over the whole energy range. 8325 1451 364 The results have been validated with existing experimental 8325 1451 365 neutron reaction cross section data, all taken from the EXFOR 8325 1451 366 database. Below 200 keV, resonance parameters are used. 8325 1451 367 8325 1451 368 - MT4 : Total inelastic cross section 8325 1451 369 8325 1451 370 Sum of MT=51-91. 8325 1451 371 8325 1451 372 - MT5 : (n,anything) cross section 8325 1451 373 8325 1451 374 For energies below 20 MeV, MT5 contains the lumped (n,gamma x) 8325 1451 375 cross section, where x may represent neutron, proton, deuteron, 8325 1451 376 triton, Helium-3 or alpha. Using the relative yields of MF6/MT5, 8325 1451 377 the (n,gamma n), (n,gamma p), ..., (n,gamma alpha) can be 8325 1451 378 recovered. These cross sections are relatively small. However, 8325 1451 379 addition of these cross sections, which can not be stored in any 8325 1451 380 other MT-number, ensures that the partial cross sections add up 8325 1451 381 to the non-elastic cross section. Above 20 MeV, MT5 contains the 8325 1451 382 total non-elastic cross section, with which the information of 8325 1451 383 MF6/MT5 can be combined to obtain particle production cross 8325 1451 384 sections and (double-)differential cross sections. 8325 1451 385 8325 1451 386 - MT16 : (n,2n) cross section 8325 1451 387 - MT17 : (n,3n) cross section 8325 1451 388 - MT22 : (n,na) cross section 8325 1451 389 - MT24 : (n,2na) cross section 8325 1451 390 - MT28 : (n,np) cross section 8325 1451 391 - MT29 : (n,n2a) cross section 8325 1451 392 - MT32 : (n,nd) cross section 8325 1451 393 - MT33 : (n,nt) cross section 8325 1451 394 - MT41 : (n,2np) cross section 8325 1451 395 - MT51-70 : (n,n') cross section for 1st-20th excited state 8325 1451 396 - MT91 : (n,n') continuum cross section 8325 1451 397 - MT102 : (n,gamma) cross section 8325 1451 398 8325 1451 399 1.0e-5 eV to 200 keV: Resonance parameters given between 30 keV 8325 1451 400 and 200 keV. At 200 keV, a background cross section of 1.5 mb 8325 1451 401 was set. 8325 1451 402 8325 1451 403 - MT103 : (n,p) cross section 8325 1451 404 - MT104 : (n,d) cross section 8325 1451 405 - MT105 : (n,t) cross section 8325 1451 406 - MT106 : (n,h) cross section 8325 1451 407 - MT107 : (n,a) cross section 8325 1451 408 - MT108 : (n,2a) cross section 8325 1451 409 - MT112 : (n,pa) cross section 8325 1451 410 - MT600-610: (n,p) cross section for 0th-10th excited state 8325 1451 411 8325 1451 412 Obtained by mapping continuum (n,p) cross section from 8325 1451 413 pre-equilibrium and compound model on discrete states. 8325 1451 414 8325 1451 415 - MT649 : (n,p) continuum cross section 8325 1451 416 - MT650-655: (n,d) cross section for 0th-5th excited state 8325 1451 417 8325 1451 418 Obtained by mapping continuum (n,d) cross section from 8325 1451 419 pre-equilibrium and compound model on discrete states. 8325 1451 420 8325 1451 421 - MT699 : (n,d) continuum cross section 8325 1451 422 - MT700-705: (n,t) cross section for 0th-5th excited state 8325 1451 423 8325 1451 424 Obtained by mapping continuum (n,t) cross section from 8325 1451 425 pre-equilibrium and compound model on discrete states. 8325 1451 426 8325 1451 427 - MT749 : (n,h) continuum cross section 8325 1451 428 - MT750-754: (n,h) cross section for 0th-4th excited state 8325 1451 429 8325 1451 430 Obtained by mapping continuum (n,h) cross section from 8325 1451 431 pre-equilibrium and compound model on discrete states. 8325 1451 432 8325 1451 433 - MT799 : (n,h) continuum cross section 8325 1451 434 - MT800-810: (n,a) cross section for 0th-10th excited state 8325 1451 435 8325 1451 436 Obtained by mapping continuum (n,a) cross section from 8325 1451 437 pre-equilibrium and compound model on discrete states. 8325 1451 438 8325 1451 439 - MT849 : (n,a) continuum cross section 8325 1451 440 8325 1451 441 ##### MF4: ANGULAR DISTRIBUTIONS OF SECONDARY PARTICLES 8325 1451 442 8325 1451 443 The versatility of MF6 for the storage of almost any secondary 8325 1451 444 distribution entails that we only use MF4 for the neutron elastic 8325 1451 445 scattering distribution. All data are generated with TALYS. 8325 1451 446 8325 1451 447 - MT2 : Elastic angular distribution 8325 1451 448 8325 1451 449 The flag LTT=3 is used to indicate a switch at 20 MeV from a 8325 1451 450 Legendre representation to a tabulated representation. For 8325 1451 451 incident energies below 20 MeV, the Legendre coefficients are 8325 1451 452 given on a sufficiently precise energy grid. They are a sum of 8325 1451 453 calculated Legendre coefficients for compound nucleus and 8325 1451 454 shape-elastic scattering. For incident energies above 20 MeV, 8325 1451 455 relative angular distributions are tabulated on an angular grid. 8325 1451 456 8325 1451 457 ##### MF6: PRODUCT ENERGY-ANGLE DISTRIBUTIONS 8325 1451 458 8325 1451 459 In MF6 we store all secondary energy, angle, and energy-angle 8325 1451 460 distributions, as well as all residual and discrete + continuum 8325 1451 461 photon production cross sections. We thus do not use MF12-15 for 8325 1451 462 the photon production that accompanies each reaction. All data 8325 1451 463 are generated with TALYS. 8325 1451 464 8325 1451 465 - MT5 : (n,anything) yields and energy-angle distributions 8325 1451 466 8325 1451 467 For energies below 20 MeV, MT5 contains the relative yields of 8325 1451 468 the (n,gamma x) reaction, where x may represent neutron, proton, 8325 1451 469 deuteron, triton, Helium-3 or alpha. Using the (n,gamma x) cross 8325 1451 470 section of MF3/MT3, the (n,gamma p), ..., (n,gamma alpha) cross 8325 1451 471 section can be recovered. For energies above 20 MeV, MT5 contains 8325 1451 472 the production yields of particles and residual products. It also 8325 1451 473 contains the secondary energy-angle distributions for all 8325 1451 474 particles and photons. First, the yields for neutrons are given 8325 1451 475 for the whole energy range. Next, on a secondary energy grid the 8325 1451 476 relative emission spectra are given together with the parameters 8325 1451 477 for the Kalbach systematics for angular distributions. Inelastic 8325 1451 478 scattering cross sections for discrete states have been broadened 8325 1451 479 and added to the continuum spectra. This procedure is repeated 8325 1451 480 for protons, deuterons, tritons, Helium-3, alpha particles and 8325 1451 481 photons. Finally, the residual production yields are given per 8325 1451 482 final product. All these yields and relative distributions can 8325 1451 483 be multiplied with the cross sections given in MF3/MT5 to get 8325 1451 484 the production cross sections and (double-)differential cross 8325 1451 485 sections. 8325 1451 486 8325 1451 487 - MT16 : (n,2n) energy-angle distr. and photon production 8325 1451 488 8325 1451 489 First, for each type of outgoing particle, the (trivial) integer 8325 1451 490 particle yields are given. Next, on a sufficiently dense incident 8325 1451 491 energy grid the secondary energy-angle distributions are 8325 1451 492 specified by means of the relative emission spectra and the 8325 1451 493 parameters for the Kalbach systematics for angular distributions. 8325 1451 494 Next, the photon yield is tabulated as a function of incident 8325 1451 495 energy. For each incident energy, the photon production is given 8325 1451 496 for all discrete gamma lines present in the final nucleus. A 8325 1451 497 continuum photon distribution is added to this. We assume 8325 1451 498 isotropy for all produced gamma rays. 8325 1451 499 8325 1451 500 For the following MT-numbers, the same procedure as for MT16 is 8325 1451 501 followed: 8325 1451 502 ----- 8325 1451 503 - MT17 : (n,3n) energy-angle distr. and photon production 8325 1451 504 - MT22 : (n,na) energy-angle distr. and photon production 8325 1451 505 - MT24 : (n,2na) energy-angle distr. and photon production 8325 1451 506 - MT28 : (n,np) energy-angle distr. and photon production 8325 1451 507 - MT29 : (n,n2a) energy-angle distr. and photon production 8325 1451 508 - MT32 : (n,nd) energy-angle distr. and photon production 8325 1451 509 - MT33 : (n,nt) energy-angle distr. and photon production 8325 1451 510 - MT41 : (n,2np) energy-angle distr. and photon production 8325 1451 511 - MT91 : (n,n') continuum energy-angle distr. and phot. prod. 8325 1451 512 - MT102 : (n,gamma) photon production 8325 1451 513 - MT108 : (n,2a) energy-angle distr. and photon production 8325 1451 514 - MT112 : (n,pa) energy-angle distr. and photon production 8325 1451 515 - MT649 : (n,p) continuum energy-angle distr. and photon prod. 8325 1451 516 - MT699 : (n,d) continuum energy-angle distr. and photon prod. 8325 1451 517 - MT749 : (n,t) continuum energy-angle distr. and photon prod. 8325 1451 518 - MT799 : (n,h) continuum energy-angle distr. and photon prod. 8325 1451 519 - MT849 : (n,a) continuum energy-angle distr. and photon prod. 8325 1451 520 ----- 8325 1451 521 8325 1451 522 - MT51 : (n,n') angular distribution and photon production 8325 1451 523 for first excited state 8325 1451 524 8325 1451 525 The angular distribution for inelastic scattering to the first 8325 1451 526 inelastic state is given with Legendre coefficients up to 20 MeV. 8325 1451 527 Next, the exclusive yields for all the discrete gamma rays that 8325 1451 528 originate from this particular level are given. 8325 1451 529 8325 1451 530 For the following MT-numbers, the same procedure as for MT51 is 8325 1451 531 followed: 8325 1451 532 ----- 8325 1451 533 - MT52-70 : (n,n') angular distribution and photon production 8325 1451 534 for 2nd-20th excited state 8325 1451 535 - MT600-610: (n,p) angular distribution and photon production 8325 1451 536 for 0th-10th excited state 8325 1451 537 - MT650-655: (n,d) angular distribution and photon production 8325 1451 538 for 0th-5th excited state 8325 1451 539 - MT700-705: (n,t) angular distribution and photon production 8325 1451 540 for 0th-5th excited state 8325 1451 541 - MT750-754: (n,h) angular distribution and photon production 8325 1451 542 for 0th-4th excited state 8325 1451 543 - MT800-810: (n,a) angular distribution and photon production 8325 1451 544 for 0th-10th excited state 8325 1451 545 ----- 8325 1451 546 8325 1451 547 ##### MF8: RADIOACTIVE DECAY DATA 8325 1451 548 8325 1451 549 For reactions to isomers, MF8 designates where the information 8325 1451 550 for isomeric versus ground state production can be found, i.e. 8325 1451 551 for each MT number it points to either MF6, MF9 or MF10. 8325 1451 552 8325 1451 553 ##### MF9: MULTIPLICITIES FOR PRODUCTION OF RADIOACTIVE NUCLIDES 8325 1451 554 8325 1451 555 All data are generated with TALYS. Final states with a lifetime 8325 1451 556 that exceeds 1 second are treated as isomer. 8325 1451 557 8325 1451 558 - MT102 : (n,gamma) cross section to ground state and isomer 8325 1451 559 8325 1451 560 ##### MF10: CROSS SECTIONS FOR PRODUCTION OF RADIOACTIVE NUCLIDES 8325 1451 561 8325 1451 562 All data are generated with TALYS. Final states with a lifetime 8325 1451 563 that exceeds 1 second are treated as isomer. 8325 1451 564 8325 1451 565 - MT106 : (n,h) cross section to ground state and isomer 8325 1451 566 8325 1451 567 ***** 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 ****8325 1451 568 8325 1451 569 This file has been checked successfully by the BNL checking 8325 1451 570 codes CHECKR-6.12, FIZCON-6.12 and PSYCHE-6.12 [dun01] and has 8325 1451 571 been processed successfully into an MCNP library by the 8325 1451 572 processing code NJOY99.81 [mac00]. 8325 1451 573 8325 1451 574 *********************** R E F E R E N C E S **********************8325 1451 575 8325 1451 576 [akk85] J.M. Akkermans and H. Gruppelaar, Phys. Lett. 157B, 95 8325 1451 577 (1985). 8325 1451 578 [alm75] E. Almen-Ramstroem, AE-report AE-503 (1975). 8325 1451 579 [ber03] O. Bersillon, Bruyeres-le-Chatel, private communication. 8325 1451 580 [bla52] J.M. Blatt and L.C. Biedenharn, Rev. Mod. 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Lecolley, in Workshop on Nuclear Data for the 8325 1451 628 Transmutation of Nuclear Waste, 2003, GSI-Darmstadt, 8325 1451 629 Germany (2003). 8325 1451 630 [mac00] R.E. Macfarlane, NJOY99 - Code system for producing 8325 1451 631 pointwise and multigroup neutron and photon cross 8325 1451 632 sections from ENDF/B Data, RSIC PSR-480 (2000). 8325 1451 633 [mad88] D.G. Madland, in Proceedings of a Specialists' Meeting on 8325 1451 634 Preequilibrium Reactions, Semmering, Austria, 8325 1451 635 February 10-12 1988, (OECD, Paris 1988), p. 103. 8325 1451 636 [mar83] A. Marcinkowski, R.W. Finlay, G. Randers-Pehrson, 8325 1451 637 C.E. Brient, R. Kurup, S. Mellema, A. Meigooni, and 8325 1451 638 R. Tailor, Nucl. Phys. A402, 220 (1983). 8325 1451 639 [mar91] A. Marcinkowski, J. Rapaport, R. Finlay, X. Aslanoglou, 8325 1451 640 and D. Kielan, Nucl. Phys. A530, 75 (1991). 8325 1451 641 [mol80] P.A. Moldauer, Nucl. Phys. A344, 185 (1980). 8325 1451 642 [mug81] S.F. Mughabghab, M. 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C16, 8325 1451 665 1792 (1977). 8325 1451 666 8325 1451 667 ************************* C O N T E N T S ************************8325 1451 668 8325 1451 669 1 451 839 18325 1451 670 2 151 108 18325 1451 671 3 1 665 18325 1451 672 3 2 665 18325 1451 673 3 3 665 18325 1451 674 3 4 29 18325 1451 675 3 5 69 18325 1451 676 3 16 12 18325 1451 677 3 17 7 18325 1451 678 3 22 29 18325 1451 679 3 24 10 18325 1451 680 3 28 16 18325 1451 681 3 32 9 18325 1451 682 3 33 8 18325 1451 683 3 41 8 18325 1451 684 3 51 29 18325 1451 685 3 52 27 18325 1451 686 3 53 26 18325 1451 687 3 54 25 18325 1451 688 3 55 25 18325 1451 689 3 56 25 18325 1451 690 3 57 24 18325 1451 691 3 58 24 18325 1451 692 3 59 23 18325 1451 693 3 60 23 18325 1451 694 3 61 23 18325 1451 695 3 62 22 18325 1451 696 3 63 22 18325 1451 697 3 64 21 18325 1451 698 3 65 21 18325 1451 699 3 66 20 18325 1451 700 3 67 20 18325 1451 701 3 68 20 18325 1451 702 3 69 19 18325 1451 703 3 70 19 18325 1451 704 3 91 19 18325 1451 705 3 102 27 18325 1451 706 3 103 32 18325 1451 707 3 104 21 18325 1451 708 3 105 17 18325 1451 709 3 106 10 18325 1451 710 3 107 29 18325 1451 711 3 108 29 18325 1451 712 3 112 29 18325 1451 713 3 600 32 18325 1451 714 3 601 24 18325 1451 715 3 602 21 18325 1451 716 3 603 20 18325 1451 717 3 604 19 18325 1451 718 3 605 19 18325 1451 719 3 606 19 18325 1451 720 3 607 18 18325 1451 721 3 608 18 18325 1451 722 3 609 18 18325 1451 723 3 610 18 18325 1451 724 3 649 17 18325 1451 725 3 650 21 18325 1451 726 3 651 17 18325 1451 727 3 652 14 18325 1451 728 3 653 13 18325 1451 729 3 654 12 18325 1451 730 3 655 12 18325 1451 731 3 699 11 18325 1451 732 3 700 17 18325 1451 733 3 701 16 18325 1451 734 3 702 15 18325 1451 735 3 703 14 18325 1451 736 3 704 13 18325 1451 737 3 705 12 18325 1451 738 3 749 11 18325 1451 739 3 750 10 18325 1451 740 3 751 9 18325 1451 741 3 752 9 18325 1451 742 3 753 9 18325 1451 743 3 754 8 18325 1451 744 3 799 7 18325 1451 745 3 800 29 18325 1451 746 3 801 29 18325 1451 747 3 802 29 18325 1451 748 3 803 29 18325 1451 749 3 804 29 18325 1451 750 3 805 29 18325 1451 751 3 806 29 18325 1451 752 3 807 29 18325 1451 753 3 808 29 18325 1451 754 3 809 29 18325 1451 755 3 810 29 18325 1451 756 3 849 29 18325 1451 757 4 2 1243 18325 1451 758 6 5 9151 18325 1451 759 6 16 758 18325 1451 760 6 17 250 18325 1451 761 6 22 1523 18325 1451 762 6 24 536 18325 1451 763 6 28 991 18325 1451 764 6 32 411 18325 1451 765 6 33 416 18325 1451 766 6 41 339 18325 1451 767 6 51 149 18325 1451 768 6 52 141 18325 1451 769 6 53 133 18325 1451 770 6 54 135 18325 1451 771 6 55 138 18325 1451 772 6 56 138 18325 1451 773 6 57 136 18325 1451 774 6 58 136 18325 1451 775 6 59 137 18325 1451 776 6 60 137 18325 1451 777 6 61 141 18325 1451 778 6 62 122 18325 1451 779 6 63 135 18325 1451 780 6 64 133 18325 1451 781 6 65 140 18325 1451 782 6 66 128 18325 1451 783 6 67 135 18325 1451 784 6 68 119 18325 1451 785 6 69 121 18325 1451 786 6 70 125 18325 1451 787 6 91 1239 18325 1451 788 6 102 1015 18325 1451 789 6 108 342 18325 1451 790 6 112 765 18325 1451 791 6 600 89 18325 1451 792 6 601 80 18325 1451 793 6 602 83 18325 1451 794 6 603 81 18325 1451 795 6 604 76 18325 1451 796 6 605 76 18325 1451 797 6 606 75 18325 1451 798 6 607 73 18325 1451 799 6 608 73 18325 1451 800 6 609 73 18325 1451 801 6 610 75 18325 1451 802 6 649 768 18325 1451 803 6 650 67 18325 1451 804 6 651 67 18325 1451 805 6 652 62 18325 1451 806 6 653 68 18325 1451 807 6 654 62 18325 1451 808 6 655 65 18325 1451 809 6 699 384 18325 1451 810 6 700 61 18325 1451 811 6 701 73 18325 1451 812 6 702 66 18325 1451 813 6 703 66 18325 1451 814 6 704 59 18325 1451 815 6 705 63 18325 1451 816 6 749 370 18325 1451 817 6 750 40 18325 1451 818 6 751 49 18325 1451 819 6 752 40 18325 1451 820 6 753 46 18325 1451 821 6 754 46 18325 1451 822 6 799 156 18325 1451 823 6 800 84 18325 1451 824 6 801 95 18325 1451 825 6 802 91 18325 1451 826 6 803 97 18325 1451 827 6 804 93 18325 1451 828 6 805 89 18325 1451 829 6 806 93 18325 1451 830 6 807 98 18325 1451 831 6 808 95 18325 1451 832 6 809 91 18325 1451 833 6 810 91 18325 1451 834 6 849 1382 18325 1451 835 8 102 3 18325 1451 836 8 106 3 18325 1451 837 9 102 57 18325 1451 838 10 106 17 18325 1451 839 8325 1 0 840 8325 0 0 841 8.320900+4 2.071852+2 0 0 1 08325 2151 842 8.320900+4 1.000000+0 0 0 1 08325 2151 843 1.000000-5 2.000000+5 1 2 0 08325 2151 844 4.500000+0 9.680000-1 0 0 2 08325 2151 845 2.071850+2 0.000000+0 0 0 342 578325 2151 846 8.000000+2 5.000000+0 4.674700+0 4.636000+0 3.870000-2 0.000000+08325 2151 847 2.310000+3 4.000000+0 1.793490+1 1.788890+1 4.600000-2 0.000000+08325 2151 848 5.112000+3 5.000000+0 5.696360+0 5.636360+0 6.000000-2 0.000000+08325 2151 849 1.209800+4 4.000000+0 2.590060+2 2.588890+2 1.170000-1 0.000000+08325 2151 850 1.551000+4 4.000000+0 1.145540+2 1.144440+2 1.100000-1 0.000000+08325 2151 851 1.782000+4 4.000000+0 6.160660-1 5.666660-1 4.940000-2 0.000000+08325 2151 852 2.390000+4 5.000000+0 1.115000-1 9.999990-2 1.150000-2 0.000000+08325 2151 853 2.704000+4 4.000000+0 2.452740+1 2.444440+1 8.299990-2 0.000000+08325 2151 854 3.290000+4 5.000000+0 9.790900-1 9.090900-1 7.000000-2 0.000000+08325 2151 855 3.331000+4 4.000000+0 2.667720+2 2.666660+2 1.060000-1 0.000000+08325 2151 856 4.554000+4 5.000000+0 1.509660+2 1.509090+2 5.700000-2 0.000000+08325 2151 857 4.985000+4 4.000000+0 9.710660+0 9.666660+0 4.400000-2 0.000000+08325 2151 858 5.268000+4 5.000000+0 2.246450+1 2.245450+1 1.000000-2 0.000000+08325 2151 859 5.361000+4 4.000000+0 5.736660+0 5.666660+0 7.000000-2 0.000000+08325 2151 860 5.373000+4 4.000000+0 4.113910+1 4.111110+1 2.800000-2 0.000000+08325 2151 861 5.420000+4 5.000000+0 1.377570+1 1.372730+1 4.840000-2 0.000000+08325 2151 862 5.685000+4 4.000000+0 5.403330+0 5.333330+0 7.000000-2 0.000000+08325 2151 863 6.160000+4 5.000000+0 7.825880+1 7.818180+1 7.700000-2 0.000000+08325 2151 864 6.913990+4 5.000000+0 4.719220+2 4.718180+2 1.040000-1 0.000000+08325 2151 865 7.267990+4 4.000000+0 2.226120+1 2.222220+1 3.900000-2 0.000000+08325 2151 866 7.306990+4 4.000000+0 5.589550+0 5.555550+0 3.400000-2 0.000000+08325 2151 867 8.162990+4 5.000000+0 1.718410+2 1.718180+2 2.300000-2 0.000000+08325 2151 868 8.518990+4 4.000000+0 2.644740+2 2.644440+2 3.000000-2 0.000000+08325 2151 869 9.408990+4 4.000000+0 3.736660+0 3.666660+0 7.000000-2 0.000000+08325 2151 870 9.534990+4 4.000000+0 4.000400+2 3.999990+2 4.100000-2 0.000000+08325 2151 871 9.944990+4 4.000000+0 6.292220+0 6.222220+0 7.000000-2 0.000000+08325 2151 872 1.024900+5 4.000000+0 7.600690+2 7.599990+2 7.000000-2 0.000000+08325 2151 873 1.073300+5 5.000000+0 9.825000+1 9.818000+1 7.000000-2 0.000000+08325 2151 874 1.087300+5 5.000000+0 1.591700+2 1.591000+2 7.000000-2 0.000000+08325 2151 875 1.126600+5 4.000000+0 4.333700+2 4.333000+2 7.000000-2 0.000000+08325 2151 876 1.180700+5 5.000000+0 3.182700+2 3.182000+2 7.000000-2 0.000000+08325 2151 877 1.227000+5 5.000000+0 3.825000+1 3.818000+1 7.000000-2 0.000000+08325 2151 878 1.323300+5 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