24-Cr- 50 ENDF/B-VI, Processed by Red Cullen using PREPRO2004 6000 0 0 0 2.40500E+4 4.95170E+1 2 0 0 52425 1451 1 0.0 0.0 0 0 0 62425 1451 2 1.00000E+0 1.50000E+8 8 5 10 62425 1451 3 0.0 0.0 1 0 427 682425 1451 4 24-Cr- 50 LANL,ORNL EVAL-OCT97 S.CHIBA,M.CHADWICK,D.HETRICK 2425 1451 5 Ch97,Ch99 DIST-SEP 1 REV4- 20010926 2425 1451 6 ----ENDF/B-VI MATERIAL 2425 REVISION 3 2425 1451 7 -----INCIDENT NEUTRON DATA 2425 1451 8 ------ENDF-6 FORMAT 2425 1451 9 2425 1451 10 ******************************************************************2425 1451 11 2425 1451 12 ENDF/B-VI MOD 5 Revision, June 2000, S.C. Frankle, R.C. Reedy, 2425 1451 13 P.G. Young (LANL) 2425 1451 14 2425 1451 15 The secondary gamma-ray spectrum for radiative capture (MF 12, 2425 1451 16 MT 102) has been updated for new experimental data at incident 2425 1451 17 neutron energies up to 1 keV. 2425 1451 18 The previous (MOD 4) pure continuum at thermal neutron energy 2425 1451 19 is replaced by 71 discrete photons. 2425 1451 20 The MF=12, MT=102 yields from 1-100 keV were adjusted slightly 2425 1451 21 to force energy conservation. 2425 1451 22 Details of these changes are described in Frankel et al. [Fr01]. 2425 1451 23 2425 1451 24 ******************************************************************2425 1451 25 2425 1451 26 ENDF/B-VI MOD 4 Evaluation, October 1997, S. Chiba, 2425 1451 27 M.B. Chadwick and P. G. Young (LANL) 2425 1451 28 2425 1451 29 Los Alamos LA150 Library, produced with FKK/GNASH/GSCAN code 2425 1451 30 in cooperation with ECN Petten. 2425 1451 31 2425 1451 32 This evaluation provides a complete representation of the 2425 1451 33 nuclear data needed for transport, damage, heating, 2425 1451 34 radioactivity, and shielding applications over the incident 2425 1451 35 neutron energy range from 1.0E-11 to 150 MeV. The discussion 2425 1451 36 here is divided into the region below and above 20 MeV. 2425 1451 37 2425 1451 38 INCIDENT NEUTRON ENERGIES < 20 MeV 2425 1451 39 2425 1451 40 Below 20 MeV the evaluation is based completely on the ENDF/B- 2425 1451 41 VI.5 (Release 2) evaluation by D. Hetrick, D. Larson, N. Larson, 2425 1451 42 and C. Y. Fu. 2425 1451 43 2425 1451 44 INCIDENT NEUTRON ENERGIES > 20 MeV 2425 1451 45 2425 1451 46 The ENDF/B-VI Release 2 evaluation extends to 20 MeV and 2425 1451 47 includes cross sections and energy-angle data for all 2425 1451 48 significant reactions. The present evaluation utilizes a more 2425 1451 49 compact composite reaction spectrum representation above 20 MeV 2425 1451 50 in order to reduce the length of the file. No essential data for 2425 1451 51 applications is lost with this representation. 2425 1451 52 The evaluation above 20 MeV utilizes MF=6, MT=5 to represent 2425 1451 53 all reaction data. Production cross sections and emission 2425 1451 54 spectra are given for neutrons, protons, deuterons, tritons, 2425 1451 55 alpha particles, gamma rays, and all residual nuclides produced 2425 1451 56 (A>5) in the reaction chains. To summarize, the ENDF sections 2425 1451 57 with non-zero data above En = 20 MeV are: 2425 1451 58 2425 1451 59 MF=3 MT= 1 Total Cross Section 2425 1451 60 MT= 2 Elastic Scattering Cross Section 2425 1451 61 MT= 3 Nonelastic Cross Section 2425 1451 62 MT= 5 Sum of Binary (n,n') and (n,x) Reactions 2425 1451 63 2425 1451 64 MF=4 MT= 2 Elastic Angular Distributions 2425 1451 65 2425 1451 66 MF=6 MT= 5 Production Cross Sections and Energy-Angle 2425 1451 67 Distributions for Emission Neutrons, Protons, 2425 1451 68 Deuterons, Tritons, and Alphas; and Angle- 2425 1451 69 Integrated Spectra for Gamma Rays and Residual 2425 1451 70 Nuclei That Are Stable Against Particle Emission 2425 1451 71 2425 1451 72 The evaluation is based on nuclear model calculations that 2425 1451 73 have been benchmarked to experimental data, especially for n + 2425 1451 74 Cr52 and p + Cr52 reactions [Ch97]. We use the GNASH code system 2425 1451 75 [Yo92], which utilizes Hauser-Feshbach statistical, 2425 1451 76 preequilibrium and direct-reaction theories. Spherical optical 2425 1451 77 model calculations are used to obtain particle transmission 2425 1451 78 coefficients for the Hauser-Feshbach calculations, as well as 2425 1451 79 for the elastic neutron angular distributions. 2425 1451 80 Cross sections and spectra for producing individual residual 2425 1451 81 nuclei are included for reactions. The energy-angle-correlations 2425 1451 82 for all outgoing particles are based on Kalbach systematics 2425 1451 83 [Ka88]. 2425 1451 84 A model was developed to calculate the energy distributions of 2425 1451 85 all recoil nuclei in the GNASH calculations [Ch96]. The recoil 2425 1451 86 energy distributions are represented in the laboratory system in 2425 1451 87 MT=5, MF=6, and are given as isotropic in the lab system. All 2425 1451 88 other data in MT=5,MF=6 are given in the center-of-mass system. 2425 1451 89 This method of representation utilizes the LCT=3 option approved 2425 1451 90 at the November, 1996, CSEWG meeting. 2425 1451 91 Preequilibrium corrections were performed in the course of the 2425 1451 92 GNASH calculations using the exciton model of Kalbach [Ka77, 2425 1451 93 Ka85], validated by comparison with calculations using Feshbach, 2425 1451 94 Kerman, Koonin (FKK) theory [Ch93]. Discrete level data from 2425 1451 95 nuclear data sheets were matched to continuum level densities 2425 1451 96 using the formulation of Ignatyuk et al. [Ig75] and pairing and 2425 1451 97 shell parameters from the Cook [Co67] analysis. Neutron and 2425 1451 98 charged- particle transmission coefficients were obtained from 2425 1451 99 the optical potentials, as discussed below. Gamma-ray 2425 1451 100 transmission coefficients were calculated using the Kopecky-Uhl 2425 1451 101 model [Ko90]. 2425 1451 102 2425 1451 103 SOME Cr-SPECIFIC INFORMATION CONCERNING THE EVAL. 2425 1451 104 2425 1451 105 The neutron total cross section was evaluated at energy grid 2425 1451 106 points by using the least-squares code GMA [Po81] taking account 2425 1451 107 of the new data measured by Dietrich et al. for natural Cr [Di97].2425 1451 108 The results were transformed to the Cr-50 cross section according 2425 1451 109 to the A*(2/3) law, i.e., by multiplying by a factor of 0.973515. 2425 1451 110 2425 1451 111 The neutron optical model potential derived for n + Cr-52 was 2425 1451 112 used for calculation of DWBA cross sections. 2425 1451 113 2425 1451 114 The transmission coefficients calculated for the n + Cr-52 2425 1451 115 evaluation were employed for all the n + Cr-50 evaluation 2425 1451 116 channels, by multiplying by a factor of 0.974192, i.e., a ratio of2425 1451 117 A**(2/3) between Cr-50 and Cr-52. 2425 1451 118 2425 1451 119 The Cr-52 transmission coefficients were calculated by using the2425 1451 120 following potentials: 2425 1451 121 2425 1451 122 For the neutron channel, the newly-searched potential for n + 2425 1451 123 Cr-52, as described in File 1 of the n + Cr-52 evaluation, was 2425 1451 124 used. 2425 1451 125 2425 1451 126 For the proton channel, a combination of 2 potentials was used :2425 1451 127 2425 1451 128 below 40 MeV : Becchetti-Greenlees [Be69] 2425 1451 129 above 40 MeV : Madland medium energy potential [Ma88] 2425 1451 130 2425 1451 131 The proton reaction cross section and transmission coefficients 2425 1451 132 below 40 MeV were multiplied by a factor of 0.845 to make the 2425 1451 133 agreement with the measured proton reaction cross section [Ca96] 2425 1451 134 better, and also to make the connection to higher energy values 2425 1451 135 smoothly. 2425 1451 136 2425 1451 137 For deuterons, the Lohr-Haeberli [Lo74] global potential was 2425 1451 138 used; for alpha particles the McFadden-Satchler [Mc66] potential 2425 1451 139 was used; and for tritons the Becchetti-Greenlees [Be71] potential2425 1451 140 was used. The He-3 channel was ignored. 2425 1451 141 2425 1451 142 The direct collective inelastic scattering to the following 2425 1451 143 levels in Cr-50 was considered by the DWBA-mode calculation of 2425 1451 144 ECIS95 [Ra96]: 2425 1451 145 2425 1451 146 Jpi Ex(MeV) Deformation length 2425 1451 147 2+ 0.786 1.063 2425 1451 148 2+ 2.922 0.479 2425 1451 149 2+ 3.156 0.591 2425 1451 150 4+ 3.317 0.4 2425 1451 151 4+ 3.621 0.565 2425 1451 152 4+ 3.692 0.447 2425 1451 153 4+ 3.898 0.214 2425 1451 154 3- 4.045 0.692 2425 1451 155 2+ 4.188 0.648 2425 1451 156 5- 4.363 0.565 2425 1451 157 3- 4.543 0.223 2425 1451 158 2+ 4.676 0.316 2425 1451 159 2+ 4.772 0.316 2425 1451 160 4+ 4.924 0.4 2425 1451 161 4+ 5.233 0.469 2425 1451 162 3- 6.45 0.264 2425 1451 163 3- 6.65 0.360 2425 1451 164 3- 6.79 0.244 2425 1451 165 3- 7.86 0.2 2425 1451 166 2425 1451 167 These data were retrieved from the literature [Bu95]. 2425 1451 168 2425 1451 169 **************************************************************** 2425 1451 170 2425 1451 171 ENDF/B-VI MOD 3 Revision, October 1997, V. McLane (NNDC) 2425 1451 172 2425 1451 173 1. Residual nucleus and AWR corrected for 49Cr in File 6, MT=16. 2425 1451 174 2. File 1 comments revised. 2425 1451 175 2425 1451 176 **************************************************************** 2425 1451 177 2425 1451 178 ENDF/B-VI MOD 2 Revision, July 1991, D. Hetrick, D. Larson, 2425 1451 179 N. Larson, and C.Y. Fu (ORNL) 2425 1451 180 2425 1451 181 1. The secondary particle distributions for MF=6,MT=51-56 were 2425 1451 182 corrected to center-of-mass, from laboratory coordinates. 2425 1451 183 2. The elastic transformation matrix was removed. 2425 1451 184 2425 1451 185 **************************************************************** 2425 1451 186 2425 1451 187 ENDF/B-VI MOD 1 Evaluation, November 1989, D. Hetrick, D. Larson,2425 1451 188 N. Larson, C. Fu (ORNL) 2425 1451 189 2425 1451 190 This work employed the Hauser-Feshbach code TNG [Fu88,Fu80, 2425 1451 191 Si86]. The TNG code provides energy and angular distributions 2425 1451 192 of particles emitted in the compound and pre-compound reactions, 2425 1451 193 ensures consistency among all reactions, and maintains energy 2425 1451 194 balance. Details pertinent to the contents of this evaluation 2425 1451 195 will be published at a later date. 2425 1451 196 2425 1451 197 Description of files ------------------------------------------- 2425 1451 198 (MF-MT) 2425 1451 199 1-451 General information, references, and definitions. 2425 1451 200 2-151 Resonance parameters; used to provide the total, 2425 1451 201 scattering, and capture cross sections from 1.E-5 eV to 2425 1451 202 792 keV. A small contribution in file 3-102 is added for 2425 1451 203 capture from 325 to 792 keV (see 3-102 below). The 2425 1451 204 resonance parameters are taken from Brusegan [Br85] with 2425 1451 205 help from brusegan et al. (private comm., 1988), and are 2425 1451 206 adjusted to give correct thermal values. The parameters 2425 1451 207 were also adjusted to the data of J.A. Harvey and H.M. 2425 1451 208 Agrawal [Ha88], and a background file is given in 3-1 from2425 1451 209 30 to 792 keV. Note that the flag has been set to allow 2425 1451 210 allow user calculation of the angular distributions from 2425 1451 211 the R-Matrix resonance parameters, if the user wants 2425 1451 212 angular distributions on a finer energy grid than given 2425 1451 213 in 4-2. 2425 1451 214 3-1 Total cross section; given by resonance parameters up to 2425 1451 215 792 keV with negative energy resonances adjusted to give 2425 1451 216 measured thermal scattering and capture cross sections 2425 1451 217 (see description for 3-102, below). Above 792 keV, 2425 1451 218 isotopic data used to 4.0 MeV [Ha88] and from 4.-20.0 MeV 2425 1451 219 high resolution natural Cr transmission measurements were 2425 1451 220 used, see Larson et al. [La88]. 2425 1451 221 3-2 Elastic scattering cross section; obtained by subtracting 2425 1451 222 the nonelastic from the total. 2425 1451 223 3-3 Nonelastic cross section; sum of 3-4, 3-16, 3-22, 2425 1451 224 3-28, 3-102, 3-103, 3-104, and 3-107. 2425 1451 225 3-4 Total inelastic cross section; sum of 3-51, 3-52, ... 2425 1451 226 ...,3-56, and 3-91 2425 1451 227 3-16 (n,2n) cross section; taken from the measurements of 2425 1451 228 Ghorai et al. [Gh87] and Ikeda et al. [Ik88]. 2425 1451 229 3-22 (n,na) cross section; calculated by the TNG code [Fu88, 2425 1451 230 Fu80,Si86]; no data available other than a emission. 2425 1451 231 3-28 (n,np) cross section; calculated by the TNG code [Fu88, 2425 1451 232 Fu80,Si86]. Little data available; 3-28 added to 3-103 2425 1451 233 agrees well with sparse p-emission data. 2425 1451 234 3-51 To 3-56 inelastic scattering exciting levels; results are 2425 1451 235 from TNG [Fu88,Fu80,Si86]. 2425 1451 236 3-91 Inelastic scattering exciting the continuum; TNG 2425 1451 237 calculated. 2425 1451 238 3-102 (n,g) capture cross section; given by resonance parameters2425 1451 239 up to 792 keV and from 792 keV to 20 MeV, TNG calculations2425 1451 240 were used but normalized to measured average capture 2425 1451 241 between 100 keV and 792 keV. A small contribution to be 2425 1451 242 added to 2-151 is given from 325 to 792 keV due to 2425 1451 243 incomplete experimental capture resonance information. 2425 1451 244 TNG calculations included a precompound component and 2425 1451 245 weighted cross sections from all isotopes of Cr give 0.82 2425 1451 246 mb at 14.5 MeV, in agreement with the measurement of 0.75 2425 1451 247 mb for natural Cr. 2425 1451 248 3-103 (n,p) cross section; calculated by the TNG code [Fu88, 2425 1451 249 Fu80,Si86]. Little data available; see 3-28 above. 2425 1451 250 3-104 (n,d) cross section; shape of (n,p) cross section used; 2425 1451 251 normalized to available data [Gr79]. 2425 1451 252 3-107 (n,a) cross section; calculated by the TNG code [Fu88, 2425 1451 253 Fu80,Si86]. 3-22 added to 3-107 agrees well with sparse 2425 1451 254 alpha-emission data. 2425 1451 255 4-2 Angular distributions of secondary neutrons for elastic 2425 1451 256 scattering; from ENDF/B-V. 2425 1451 257 If desired, angular distributions can be calculated by 2425 1451 258 the user on a finer energy grid from the R-matrix 2425 1451 259 resonance parameters in 2-151. 2425 1451 260 6-16 (n,2n) reaction; includes simple constant yields for the 2425 1451 261 neutron and 49Cr residual, and energy dependent yield 2425 1451 262 based on TNG calculated gamma-ray spectra for the gamma 2425 1451 263 ray; TNG calculated normalized distributions are given for2425 1451 264 each product. Isotropy is assumed. 2425 1451 265 6-22 (n,na) reaction; includes simple constant yields for the 2425 1451 266 neutron, alpha, and 46Ti residual, and energy dependent 2425 1451 267 yield based on tng calculated gamma-ray spectra for the 2425 1451 268 gamma ray; calculated normalized distributions are given 2425 1451 269 for each product. Isotropy is assumed. 2425 1451 270 6-28 (n,np) reaction; includes simple constant yields for the 2425 1451 271 neutron and 49V residual, and energy dependent yield 2425 1451 272 based on TNG calculated gamma-ray spectra for the gamma 2425 1451 273 ray; calculated normalized distributions are given for 2425 1451 274 each product. Isotropy is assumed. (n,xp) d-d emission 2425 1451 275 data used to benchmark the calculation. 2425 1451 276 6-51 through 6-56 inelastic scattering exciting levels; 2425 1451 277 assumed isotropic. 2425 1451 278 6-91 Inelastic scattering exciting the continuum; includes 2425 1451 279 simple constant yields for the neutron and 50Cr residual 2425 1451 280 and energy dependent yield based on TNG calculated 2425 1451 281 gamma-ray spectra for the gamma ray; TNG calculated 2425 1451 282 normalized distributions are given for each. Isotropy 2425 1451 283 is assumed. 2425 1451 284 6-103 (n,p) reaction; includes simple constant yields for p 2425 1451 285 and 50V residual, and energy dependent yield based 2425 1451 286 on calculated gamma-ray spectra for gamma ray; 2425 1451 287 calculated normalized distributions are given for each 2425 1451 288 product. Isotropy is assumed. (n,xp) d-d emission data 2425 1451 289 used to benchmark the calculation. 2425 1451 290 6-107 (n,a) reaction; includes simple constant yields for alpha 2425 1451 291 and 47Ti residual, and energy dependent yield based 2425 1451 292 on calculated gamma-ray spectra for gamma ray; calculated 2425 1451 293 normalized distributions are given for each product. 2425 1451 294 Isotropy is assumed. (n,xa) d-d emission data used to 2425 1451 295 benchmark the calculation. 2425 1451 296 12-51 through 12-56 branching ratios for the levels are given. 2425 1451 297 12-102 (n,g) capture; TNG calculated. 2425 1451 298 14-51 through 14-56 and 14-102 gamma ray angular distributions; 2425 1451 299 assumed to be isotropic. 2425 1451 300 15-102 (n,g) capture; TNG calculated. 2425 1451 301 2425 1451 302 ---------------------------------------------------------------- 2425 1451 303 Uncertainty files 2425 1451 304 An LB=8 section is included for all non-derived files as 2425 1451 305 required by ENDF/B-VI. 2425 1451 306 2425 1451 307 33-1 Uncertainties are derived from 1.E-5 to 100 eV. From 100 2425 1451 308 eV to 20 MeV they are explicit, using LB=0,1 and 8. 2425 1451 309 33-2 From 1.E-5 to 100 eV, uncertainties are explicit, based 2425 1451 310 upon thermal uncertainty and other data. From 100 eV to 2425 1451 311 20 MeV the files are derived. 2425 1451 312 33-3 From 1.E-5 to 792 keV uncertainties are derived. From 2425 1451 313 792 keV to 20 MeV uncertainties are explicit, using LB=1 2425 1451 314 and 8. 2425 1451 315 33-4 Uncertainties are all derived. 2425 1451 316 33-16 Uncertainties for (n,2n) are explicit, estimated from TNG.2425 1451 317 33-22 Uncertainties for (n,na) are explicit, estimated from TNG.2425 1451 318 33-28 Uncertainties for (n,np) are explicit, estimated from TNG.2425 1451 319 33-51 through 3-91 Uncertainties for inelastic scattering are 2425 1451 320 explicit, based on data and calculation uncertainties. 2425 1451 321 33-102 Uncertainties are explicit, based on thermal data at low 2425 1451 322 energies, and calculated results above 792 keV. 2425 1451 323 33-104 Uncertainties estimated, based on data. 2425 1451 324 33-103 Uncertainties estimated from TNG. 2425 1451 325 33-107 Uncertainties estimated from TNG. 2425 1451 326 2425 1451 327 **************************************************************** 2425 1451 328 2425 1451 329 REFERENCES 2425 1451 330 2425 1451 331 [Be69] F.D. Becchetti, Jr., and G.W. Greenlees, Phys.Rev. 182, 2425 1451 332 1190 (1969) 2425 1451 333 [Be71] F.D. Becchetti, Jr., and G.W. Greenlees, Polarization 2425 1451 334 Phenomena in Nuclear Reactions, Proc. Conf. (Ed: H.H. 2425 1451 335 Barschall and W. Haeberli, The University of Wisconsin Press, 2425 1451 336 1971) p.682 2425 1451 337 [Br85] A. Brusegan, R. Buyl, F.Corvi, et al., Nuclear Data for 2425 1451 338 Basic and Applied Science, Proc.Conf., Santa Fe, NM, May 1985, 2425 1451 339 (Gordon and Breach, 1986) p. 633 2425 1451 340 [Bu95] T.W. Burrows, Nucl.Data Sheets, 75, 1 (1995) 2425 1451 341 [Ca96] R.F. Carlson, Atomic Data and Nuclear Data Tables, 63, 2425 1451 342 93 (1996) 2425 1451 343 [Ch93] M.B. Chadwick and P.G. Young, Phys. Rev. C 47, 2255 (1993)2425 1451 344 [Ch96] M.B. Chadwick, P.G. Young, R.E. MacFarlane, and A.J. 2425 1451 345 Koning, "High-Energy Nuclear Data Libraries for Accelerator- 2425 1451 346 Driven Technologies: Calculational Method for Heavy Recoils," 2425 1451 347 Proc. of 2nd Int. Conf. on Accelerator Driven Transmutation 2425 1451 348 Technology and Applications, Kalmar, Sweden, 3-7 June 1996. 2425 1451 349 [Ch97] M.B. Chadwick and P.G. Young, "Model Calculations of 2425 1451 350 n,p + 58,60,61,62,64Ni" in APT PROGRESS REPORT: 1 August - 1 2425 1451 351 September 1997, internal Los Alamos National Laboratory memo T-2425 1451 352 2-97/MS-51, 8 September 1997 from R.E. MacFarlane to L. Waters.2425 1451 353 [Co67] J.L. Cook, H. Ferguson, and A.R. De L Musgrove, Aust.J. 2425 1451 354 Phys. 20, 477 (1967) 2425 1451 355 [Ch99] M.B. Chadwick, P G. Young, G. M. Hale, et al., Los Alamos 2425 1451 356 National Laboratory report, LA-UR-99-1222 (1999) 2425 1451 357 [De89] J.P. Delaroche, Y. Wang and J. Rapaport, Phys.Rev. C 39, 2425 1451 358 391 (1989) 2425 1451 359 [Di97] F. Dietrich et al., private communication (1997) 2425 1451 360 [Fr01] S.C. Frankle, R.C. Reedy, and P.G. Young, Los ALamos 2425 1451 361 National Laboratory Report, LA-13812 (2001). 2425 1451 362 [Fu88] C.Y. Fu, Oak Ridge National Laboratory report 2425 1451 363 ORNL/TM-7042 (1980) and Nucl.Sci.Eng. 100, 61 (1988) 2425 1451 364 [Fu80] C.Y Fu, Symp. on Neutron Cross Sections from 10 to 50 MeV,2425 1451 365 Upton, NY, May 1980, Brookhaven National Laboratory report 2425 1451 366 BNL-NCS-51425 (1980) p.675 2425 1451 367 [Gh87] S.K. Ghorai, J.R. Williams, and W.L. Alford, J.Phys.G 13, 2425 1451 368 405 (1987) 2425 1451 369 [Gr79] S.M. Grimes, R.C. Haight, K.R. Alvar, et al., Phys.Rev. C 2425 1451 370 19, 2127 (1979) 2425 1451 371 [Ha88] J.A. Harvey and H.M. Agrawal, private communication (1988)2425 1451 372 [Ig75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov.J. 2425 1451 373 Nucl.Phys. 21, 255 (1975); translation of Yad.Fiz. 21, 485 2425 1451 374 (1975) 2425 1451 375 [Ik88] Y. Ikeda, C. Konno, K. Oishi, T. Nakamura, H. Miyade, K. 2425 1451 376 Kawade, H. Yamamoto, and T. Katoh, report JAERI 1312 (1988) 2425 1451 377 [Ka77] C. Kalbach, Z.Phys.A 283, 401 (1977) 2425 1451 378 [Ka85] C. Kalbach, Los Alamos National Laboratory report 2425 1451 379 LA-10248-MS (1985) 2425 1451 380 [Ka88] C. Kalbach, Phys.Rev. C 37, 2350 (1988); see also 2425 1451 381 C. Kalbach and F.M. Mann, Phys.Rev. C 23, 112 (1981) 2425 1451 382 [Ki74] W.E. Kinney et al., report ORNL-4806 (1974) 2425 1451 383 [Ko90] J. Kopecky and M. Uhl, Phys.Rev. C 41, 1941 (1990) 2425 1451 384 [La88] D.C. Larson, J.A. Harvey, and N.W. Hill, private comm. 2425 1451 385 (1988) 2425 1451 386 [Lo74] J.M.Lohr and W.Haeberli, Nucl.Phys. A232,381(1974) 2425 1451 387 [Ma88] D.G. Madland, Proc. OECD/NEANDC Specialist's Meeting on 2425 1451 388 Preequilibrium Nuclear Reactions, Semmering, Austria, Feb. 2425 1451 389 1988, NEANDC-245 (1988) p.103 2425 1451 390 [Mc66] L. McFadden and G.R. Satchler, Nucl.Phys. 84, 177 (1966) 2425 1451 391 [Mu81] S.F. Mughabghab, M. Divadeenam and N.E. Holden, "Neutron 2425 1451 392 Cross Sections", Vol.1, Part A, (Academic Press, 1981) 2425 1451 393 [Ol87] N. Olsson et al, Nucl.Phys. A472, 237 (1987) 2425 1451 394 [Po81] W. Poenitz, Proc. Conf. on Nuclear Data Evaluation Methods2425 1451 395 and Procedures, Brookhaven National Laboratory Report BNL-NCS- 2425 1451 396 51363, Vol.1 (1981) p.249 2425 1451 397 [Ra96] J. Raynal, "Notes on ECIS94", Service de Physique 2425 1451 398 Theorique, Saclay, France (private communication through A.J. 2425 1451 399 Koning, 1996) 2425 1451 400 [Si86] K. Shibata and C.Y. Fu, Oak Ridge National Laboratory 2425 1451 401 report ORNL/TM-10093 (1986) 2425 1451 402 [Sm91] D.L. Smith, "Probability, Statistics, and Data Uncertainty2425 1451 403 in Nuclear Science and Technology" (American Nuclear Society, 2425 1451 404 1991) 2425 1451 405 [Yo92] P.G. Young, E.D. Arthur, and M.B. Chadwick, report 2425 1451 406 LA-12343-MS (1992) 2425 1451 407 2425 1451 408 ************************ C O N T E N T S *********************** 2425 1451 409 ***************** Program LINEAR (VERSION 2004-1) ***************2425 1451 410 For All Data Greater than 1.0000E-10 barns in Absolute Value 2425 1451 411 Data Linearized to Within an Accuracy of .100000000 per-cent 2425 1451 412 ***************** Program RECENT (VERSION 2004-1) ***************2425 1451 413 for All Data Greater than 1.0000E-10 barns in Absolute Value 2425 1451 414 Data Linearized to within an Accuracy of .100000000 per-cent 2425 1451 415 ***************** Program FIXUP (Version 2004-1) ****************2425 1451 416 Corrected ZA/AWR in All Sections-----------------------------Yes 2425 1451 417 Corrected Thresholds-----------------------------------------No 2425 1451 418 Extended Cross Sections to 20 MeV----------------------------No 2425 1451 419 Allow Cross Section Deletion---------------------------------No 2425 1451 420 Allow Cross Section Reconstruction---------------------------Yes 2425 1451 421 Make All Cross Sections Non-Negative-------------------------Yes 2425 1451 422 Delete Energies Not in Ascending Order-----------------------Yes 2425 1451 423 Deleted Duplicate Points-------------------------------------Yes 2425 1451 424 Check for Ascending MAT/MF/MT Order--------------------------Yes 2425 1451 425 Check for Legal MF/MT Numbers--------------------------------Yes 2425 1451 426 Allow Creation of Missing Sections---------------------------No 2425 1451 427 Allow Insertion of Energy Points-----------------------------No 2425 1451 428 Create Uniform Energy Grid-----------------------------------No 2425 1451 429 Delete Section if Cross Section =0 at All Energies-----------Yes 2425 1451 430 **************** Program DICTIN (VERSION 2004-1) ****************2425 1451 431 1 451 499 52425 1451 432 2 151 393 12425 1451 433 3 1 39540 42425 1451 434 3 2 39523 42425 1451 435 3 3 38811 42425 1451 436 3 4 17 12425 1451 437 3 5 10 42425 1451 438 3 16 7 12425 1451 439 3 22 6 12425 1451 440 3 28 7 12425 1451 441 3 51 15 12425 1451 442 3 52 13 12425 1451 443 3 53 12 12425 1451 444 3 54 11 12425 1451 445 3 55 11 12425 1451 446 3 56 11 12425 1451 447 3 91 11 12425 1451 448 3 102 38793 12425 1451 449 3 103 14 12425 1451 450 3 104 6 12425 1451 451 3 107 13 12425 1451 452 4 2 4248 42425 1451 453 6 5 12700 42425 1451 454 6 16 150 32425 1451 455 6 22 244 12425 1451 456 6 28 338 12425 1451 457 6 51 7 22425 1451 458 6 52 7 22425 1451 459 6 53 7 22425 1451 460 6 54 7 22425 1451 461 6 55 7 22425 1451 462 6 56 7 22425 1451 463 6 91 901 12425 1451 464 6 103 892 12425 1451 465 6 107 956 12425 1451 466 12 51 3 12425 1451 467 12 52 3 12425 1451 468 12 53 3 12425 1451 469 12 54 3 12425 1451 470 12 55 3 12425 1451 471 12 56 3 12425 1451 472 12 102 297 52425 1451 473 14 51 1 12425 1451 474 14 52 1 12425 1451 475 14 53 1 12425 1451 476 14 54 1 12425 1451 477 14 55 1 12425 1451 478 14 56 1 12425 1451 479 14 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