20-Ca-Nat ENDF/B-VI, Processed by Red Cullen using PREPRO2004 6000 0 0 0 2.00000E+4 3.97360E+1 0 0 0 22000 1451 1 0.0 0.0 0 0 0 62000 1451 2 1.00000E+0 1.50000E+8 8 0 10 62000 1451 3 0.0 0.0 1 0 411 862000 1451 4 20-Ca- 0 LANL,ORNL EVAL-MAR97 M.B.CHADWICK,P.G.YOUNG,C.Y.FU 2000 1451 5 Ch97,Ch99,Fu91 DIST-SEP 1 REV1- 20010926 2000 1451 6 ----ENDF/B-VI MATERIAL 2000 2000 1451 7 -----INCIDENT NEUTRON DATA 2000 1451 8 ------ENDF-6 FORMAT 2000 1451 9 2000 1451 10 ******************************************************************2000 1451 11 2000 1451 12 ENDF/B-VI MOD 1 Revision, October 2000, S.C.Frankle, R.C.Reedy, 2000 1451 13 P.G.Young (LANL) 2000 1451 14 2000 1451 15 The secondary gamma-ray spectrum for radiative capture 2000 1451 16 (MT=102) has been changed for incident neutron energies 2000 1451 17 below 20 MeV. The previous evaluation (MOD 1) utilized a pure 2000 1451 18 continuum representation at all incident energies. We have 2000 1451 19 replaced this with 31 discrete gamma rays and a continuum 2000 1451 20 constructed by binning another 417 weaker discrete gamma rays. 2000 1451 21 This new MT=102 data evaluation is based upon an analysis 2000 1451 22 of thermal neutron-induced experimental data. 2000 1451 23 The Q-value for radiative capture was also updated in File 3. 2000 1451 24 Details of these changes are described in Frankel et al. [Fr01]. 2000 1451 25 2000 1451 26 ******************************************************************2000 1451 27 2000 1451 28 ENDF/B-VI MOD 1 Evaluation, March 1997, M.B. Chadwick and 2000 1451 29 P.G. Young (LANL) 2000 1451 30 2000 1451 31 Los Alamos LA150 Library, produced with FKK/GNASH/GSCAN code 2000 1451 32 in cooperation with ECN Petten. 2000 1451 33 2000 1451 34 This evaluation provides a complete representation of the 2000 1451 35 nuclear data needed for transport, damage, heating, 2000 1451 36 radioactivity, and shielding applications over the incident 2000 1451 37 neutron energy range from 1.0E-11 to 150 MeV. The discussion 2000 1451 38 here is divided into the region below and above 20 MeV. 2000 1451 39 2000 1451 40 INCIDENT NEUTRON ENERGIES < 20 MeV 2000 1451 41 2000 1451 42 Below 20 MeV the evaluation is based completely on the ENDF/B- 2000 1451 43 VI.1 (Release 0) evaluation by C.Y.Fu and D.M.Hetrick [Fu91]. 2000 1451 44 2000 1451 45 INCIDENT NEUTRON ENERGIES > 20 MeV (40Ca calcs) 2000 1451 46 2000 1451 47 The ENDF/B-VI Release 3 evaluation extends to 40 MeV and 2000 1451 48 includes cross sections and energy-angle data for all 2000 1451 49 significant reactions. The present evauation utilizes a more 2000 1451 50 compact composite reaction spectrum representation above 20 MeV 2000 1451 51 in order to reduce the length of the file. No essential data for 2000 1451 52 applications is lost with this representation. Additionally, we 2000 1451 53 have modified the neutron reaction cross sections slightly to 2000 1451 54 improve agreement with data above 20 MeV. 2000 1451 55 The evaluation above 20 MeV utilizes MF=6, MT=5 to represent 2000 1451 56 all reaction data. Production cross sections and emission 2000 1451 57 spectra are given for neutrons, protons, deuterons, tritons, 2000 1451 58 alpha particles, gamma rays, and all residual nuclides produced 2000 1451 59 (A>5) in the reaction chains. To summarize, the ENDF sections 2000 1451 60 with non-zero data above En = 20 MeV are: 2000 1451 61 2000 1451 62 MF=3 MT= 1 Total Cross Section 2000 1451 63 MT= 2 Elastic Scattering Cross Section 2000 1451 64 MT= 3 Nonelastic Cross Section 2000 1451 65 MT= 5 Sum of Binary (n,n') and (n,x) Reactions 2000 1451 66 2000 1451 67 MF=4 MT= 2 Elastic Angular Distributions 2000 1451 68 2000 1451 69 MF=6 MT= 5 Production Cross Sections and Energy-Angle 2000 1451 70 Distributions for Emission Neutrons, Protons, 2000 1451 71 Deuterons, and Alphas; and Angle-Integrated 2000 1451 72 Spectra for Gamma Rays and Residual Nuclei That 2000 1451 73 Are Stable Against Particle Emission 2000 1451 74 2000 1451 75 The evaluation is based on nuclear model calculations that 2000 1451 76 have been benchmarked to experimental data. We use the GNASH 2000 1451 77 code system [Yo92], which utilizes Hauser-Feshbach statistical, 2000 1451 78 preequilibrium and direct-reaction theories. Spherical optical 2000 1451 79 model calculations are used to obtain particle transmission 2000 1451 80 coefficients for the Hauser-Feshbach calculations, as well as 2000 1451 81 for the elastic neutron angular distributions. 2000 1451 82 Cross sections and spectra for producing individual residual 2000 1451 83 nuclei are included for reactions that exceed a cross section of 2000 1451 84 approximately 1 nb at any energy. The energy-angle-correlations 2000 1451 85 for all outgoing particles are based on Kalbach systematics 2000 1451 86 [Ka88]. 2000 1451 87 A model was developed to calculate the energy distributions of 2000 1451 88 all recoil nuclei in the GNASH calculations [Ch96a]. The recoil 2000 1451 89 energy distributions are represented in the laboratory system in 2000 1451 90 MT=5, MF=6, and are given as isotropic in the lab system. All 2000 1451 91 other data in MT=5,MF=6 are given in the center-of-mass system. 2000 1451 92 This method of representation utilizes the LCT=3 option approved 2000 1451 93 at the November, 1996, CSEWG meeting.. 2000 1451 94 The starting point for this evaluation was the previous 2000 1451 95 Livermore (1995) evaluation by Chadwick and Young for neutrons up 2000 1451 96 to 100 MeV [Ch95], and protons up to 250 MeV [Ch96b]. The main 2000 1451 97 additions in the current work were: (1) Extension of the neutron 2000 1451 98 calculations to higher energies; (2) Inclusion of direct inelastic2000 1451 99 scattering to low-lying collective states using ECIS; (3) 2000 1451 100 inclusion of a renormalization of the calculated results to 2000 1451 101 circumvent a numerical inaccuracy at higher incident energies 2000 1451 102 (>150 MeV) which ensure the individual reactions sum to the 2000 1451 103 evaluated nonelastic cross section; (4) inclusion of A>4 nuclide 2000 1451 104 production and nuclide energy spectra; (5) inclusion of triton 2000 1451 105 emission; and (6) utilization of ENDF-6 format. 2000 1451 106 The neutron total cross section was evaluated from available 2000 1451 107 experimental data. The evaluation was based primarily on Finlay's2000 1451 108 1993 high-accuracy measurements [Fi93]. 2000 1451 109 The optical potential of Islam [Is88] specially developed for 2000 1451 110 n+Ca elastic scattering, was used for 20-60 MeV neutrons, and 2000 1451 111 above this energy the Madland global potential was used [Ma88]. 2000 1451 112 The Wilmore-Hodgson potential was used below 20 MeV [Wi64]. For 2000 1451 113 incident protons, the Islam neutron potential was modified to 2000 1451 114 account for proton scattering from 20 to 60 MeV, and again the 2000 1451 115 Madland global potential was used at higher energies. The 2000 1451 116 Becchetti-Greenlees potential was used for protons below 20 MeV 2000 1451 117 [Be69]. For deuterons, tritons and alphas the method of Watanabe,2000 1451 118 which uses a modified Perey potential [Pe63], was applied at all 2000 1451 119 energies [Ma88]. 2000 1451 120 Direct inelastic scattering to the low-lying collective states 2000 1451 121 was calculated with the ECIS code. Deformation lengths were taken 2000 1451 122 from the works of Alarcon and Rapaport [8] and Honore et al. 2000 1451 123 [Ho86], giving: 3- (Ex= 3.736 MeV, delta=1.340), 2+ (Ex=3.904, 2000 1451 124 delta=0.360), and 5- (Ex=4.492, delta=0.930). 2000 1451 125 While the above optical potentials did describe the experimental2000 1451 126 neutron and proton nonelastic cross section data fairly well, we 2000 1451 127 modified these theoretical predictions slightly to better agree 2000 1451 128 with the measurements, and renormalized the transmission 2000 1451 129 coefficients accordingly. The calculated neutron elastic 2000 1451 130 scattering distributions agree well with experimental data. 2000 1451 131 Nuclear level densities were taken from the Ignatyuk model 2000 1451 132 [Ig75], which includes a washing out of shell effects with 2000 1451 133 increasing excitation energy, and gamma-ray strength functions 2000 1451 134 were obtained from the model of Kopecky and Uhl [Ko90]. 2000 1451 135 The existing ENDF/B-VI evaluation below 20 MeV was performed at 2000 1451 136 Oak Ridge, for natural Calcium. Since 40Ca makes up 2000 1451 137 approximately 97% of natural calcium, we have combined the 2000 1451 138 natural evaluation below 20 MeV with our new 40Ca evaluation 2000 1451 139 above 20 MeV. The combined evaluation up to 150 MeV can be 2000 1451 140 treated as a natural evaluation to a good approximation. Using 2000 1451 141 our 40Ca for natural Ca above 20 MeV is a very good 2000 1451 142 approximation for transport and heating applications; although 2000 1451 143 our evaluation above 20 MeV does omit the production of 2000 1451 144 radionuclides with A>40 (the practical consequences of this are 2000 1451 145 expected to be small). 2000 1451 146 2000 1451 147 **************************************************************** 2000 1451 148 2000 1451 149 ENDF/B-VI MOD 0 Evaluation, October 1980, C.Y. Fu and 2000 1451 150 D.M. Hetrick (ORNL) 2000 1451 151 2000 1451 152 ENDF/B-V Material 1320 converted to ENDF-6 format by NNDC. 2000 1451 153 2000 1451 154 DNA 4152 MOD 5 (OCT 1980) 2000 1451 155 This evaluation supersedes the DNA 4152 MOD 4. The energy 2000 1451 156 range from 8.0 to 20.0 MeV was completely reevaluated 2000 1451 157 documentation is in preperation. 2000 1451 158 2000 1451 159 **************************************************************** 2000 1451 160 2000 1451 161 DNA 4152 MOD 4, Sep 1976, C.Y. Fu and F.G. Perey (ORNL) 2000 1451 162 2000 1451 163 Total cross sections from 100 eV to 50 keV were decreased by 2000 1451 164 about 200 mb according to new measurement [Si74]. Both the new 2000 1451 165 data and the earlier evaluation are given graphically in BNL-325 2000 1451 166 [Ga76]. 2000 1451 167 Capture cross sections from 2.5 keV to 200 keV were increased 2000 1451 168 by a factor of 2 to 5 according to new ORELA data [Al75,Mu76]. 2000 1451 169 The capture cross sections were assumed to decrease above 200 2000 1451 170 keV, reach a minimum near 5 MeV, then increase to go through a 2000 1451 171 14-MeV datum by Cvelbar et al [Cv67]. 2000 1451 172 (n,x) and (n,xg) cross sections for MT=4, 22, 28, 103, 2000 1451 173 and 107 above 10 MeV were revised based on the the calculation 2000 1451 174 reported in Fu [Fu76]. The calculated (n,xg) cross sections 2000 1451 175 agree with ORELA measurement by Dickens et al. [Di74] but were 2000 1451 176 separately given for each reaction. 2000 1451 177 In addition, two minor changes were made: Q(n,2n) was changed 2000 1451 178 to that of 48Ca to include a small contribution from this 2000 1451 179 isotope. Three points were added to the total cross section 2000 1451 180 from 1.18 to 1.19 MeV to define a cross-section minimum better. 2000 1451 181 2000 1451 182 ******************************************************************2000 1451 183 2000 1451 184 ENDF/B-III Evaluation, February 1973, C.Y. Fu and F.G. Perey 2000 1451 185 (ORNL) 2000 1451 186 2000 1451 187 DNA 4152 MOD 3 2000 1451 188 Incorporates into MOD 2 the results of extensive nuclear 2000 1451 189 nuclear model calculations and several recent data sets. 2000 1451 190 F.G. Perey (ORNL). 2000 1451 191 2000 1451 192 DESCRIPTION OF DNA 4152 MOD 3----- 2000 1451 193 2000 1451 194 FILE 1 GENERAL INFORMATION 2000 1451 195 SECTION 451 DISCRIPTIVE DATA AND DICTIONARY 2000 1451 196 FILE 2 RESONANCE PARAMETERS 2000 1451 197 SECTION 151 GENERAL DESIGNATION FOR RESONANCE INFORMATION 2000 1451 198 ONLY EFFECTIVE SCATTERING LENGTH GIVEN. TAKEN FROM BNL-325. 2000 1451 199 FILE 3 NEUTRON CROSS SECTIONS 2000 1451 200 SECTION 1 TOTAL INTERACTION 2000 1451 201 0.00001 EV TO 10 EV -- ASSUMED TO BE THE SUM OF A CONSTANT 2000 1451 202 SCATERING CROSS SECTION AND THE CAPTURE CROSS SECTION. 2000 1451 203 10 EV TO 10 KEV -- MAGLEBY ET. AL.(DRAKE EVALUATION) 2000 1451 204 10 KEV TO 180 KEV -- DUKE MEASUREMENTS.(DRAKE EVALUATION) 2000 1451 205 180 KEV TO 480 KEV -- ORNL MEASUREMENT. 2000 1451 206 480 KEV TO 500 KEV -- AVERAGE OF ORNL AND NBS MEASUREMENTS. 2000 1451 207 500 KEV TO 20 MEV -- WEIGHTED AVERAGE OF ORNL, NBS AND 2000 1451 208 KARLSRUHE DATA. 2000 1451 209 SECTION 2 ELASTIC SCATTERING 2000 1451 210 DERIVED BY SUBTRACTING THE NON-ELASTIC CROSS SECTION FROM THE 2000 1451 211 TOTAL CROSS SECTION. RESULTING CROSS SECTION CHECKS WELL 2000 1451 212 WITH AVAILABLE DATA. 2000 1451 213 SECTION 3 NON-ELASTIC INTERACTION 2000 1451 214 CALCULATION FITTING MEASURED DATA. 2000 1451 215 SECTION 4 TOTAL INELASTIC SCATTERING 2000 1451 216 DERIVED BY SUMMING THE PARTIAL CROSS SECTIONS. 2000 1451 217 SECTION 16 (N,2N) REACTION 2000 1451 218 CURVE DRAWN THROUGH EXPERIMENTAL DATA. 2000 1451 219 SECTION 22 (N,NA) REACTION 2000 1451 220 SUM OF CALCULATED (N,NA) AND (N,AN) CROSS SECTIONS. 2000 1451 221 CALCULATION FITS MEASURED (N,NA) BUT NO DATA AVAILABLE FOR 2000 1451 222 (N,AN). 2000 1451 223 SECTION 28 (N,NP) REACTION 2000 1451 224 SUM OF CALCULATED (N,NP) AND (N,PN) CROSS SECTIONS. 2000 1451 225 CALCULATION FITS MEASURED (N,NP) BUT NO DATA AVAILABLE FOR 2000 1451 226 (N,PN). 2000 1451 227 SECTION 51 THROUGH 73 INELASTIC SCATTERING EXCITING LEVELS 2000 1451 228 SECTION 51 FIRST EXCITED STATE IN CA-44. DATA GIVEN IS 2000 1451 229 ASSUMED. 2000 1451 230 SECTION 52 TO 64 FIRST 13 EXCITED STATES IN CALCIUM-40. 2000 1451 231 CALCULATED. GOOD AGREEMENT WITH AVAILABLE DATA. 2000 1451 232 SECTION 65 TO 73 FROM MERGING 35 LEVEL IN CA-40. CALCULATED. 2000 1451 233 SECTION 91 INELASTIC SCATERING EXCITING THE CONTINUUM 2000 1451 234 CALCULATED. 2000 1451 235 SECTION 102 RADIATIVE CAPTURE 2000 1451 236 1/V UP TO 1.0 KEV. RESONANCE CROSS SECTION IS BASED ON 2000 1451 237 DRAKE S CALCULATION ASSUMING A CONSTANT RADIATION WIDTH OF 2000 1451 238 2.5 EV. RESONANCE CAPTURE DATA HAVE BEEN TAKEN BY R. L. 2000 1451 239 MACKLIN OF ORNL USING ORELA BUT HAVE NOT BEEN REDUCED. 2000 1451 240 SECTION 103 (N,P) REACTION 2000 1451 241 CALCULATION FITTING EXPERIMENTAL DATA. 2000 1451 242 SECTION 104 (N,D) REACTION 2000 1451 243 CALCULATION FITTING EXPERIMENTAL DATA. 2000 1451 244 SECTION 105 (N,T) REACTION 2000 1451 245 CALCULATED. 2000 1451 246 SECTION 106 (N,HE-3) REACTION 2000 1451 247 CALCULATED. 2000 1451 248 SECTION 107 (N,A) REACTION 2000 1451 249 CALCULATED, COMPARED FAVORABLY WITH EXPERIMENTS. 2000 1451 250 SECTION 108 (N,2A) REACTION 2000 1451 251 CALCULATED. 2000 1451 252 SECTION 111 (N,2P) REACTION 2000 1451 253 CALCULATED. 2000 1451 254 SECTION 112 (N,PA) REACTION 2000 1451 255 CALCULATED. 2000 1451 256 SECTION 251 MU BAR 2000 1451 257 DERIVED FROM ELASTIC ANGULAR DISTRIBUTION USING THE COMPUTER 2000 1451 258 CODE SAD. 2000 1451 259 SECTION 252 XI 2000 1451 260 SEE SECTION 251. 2000 1451 261 SECTION 253 GAMMA 2000 1451 262 SEE SECTION 251. 2000 1451 263 FILE 4 ANGULAR DISTRIBUTION OF SECONDARY NEUTRONS 2000 1451 264 ALL DISTRIBUTIONS ARE GIVEN IN THE LEGENDRE POLYNOMIAL 2000 1451 265 REPRESENTATIONS. 2000 1451 266 SECTION 2 ELASTIC SCATTERING 2000 1451 267 0.00001 EV TO .01 MEV-- ASSUMED ISOTROPIC. 2000 1451 268 .01 MEV TO 4.0 MEV -- FROM EXPERIMENT. 2000 1451 269 4.0 MEV TO 20.0 MEV-- CALCULATION FITTING AVAILABLE DATA. 2000 1451 270 REPRESENTATION IS IN THE CENTER OF MASS SYSTEM. 2000 1451 271 TRANSFORMATION MATRIX IS GIVEN. 2000 1451 272 SECTION 16 (N,2N) REACTION 2000 1451 273 ASSUMED ISOTROPIC IN THE CENTER OF MASS FRAME. 2000 1451 274 SECTION 22 (N,NA) REACTION 2000 1451 275 ASSUMED ISOTROPIC IN THE CENTER OF MASS FRAME. 2000 1451 276 SECTION 28 (N,NP) REACTION 2000 1451 277 ASSUMED ISOTROPIC IN THE CENTER OF MASS FRAME. 2000 1451 278 SECTION 51 INELASTIC SCATTERING EXCITING FIRST LEVEL 2000 1451 279 ASSUMED ISOTROPIC IN THE CENTER OF MASS FRAME. 2000 1451 280 SECTION 52 THROUGH 64 2000 1451 281 CALCULATED. REPRESENTATION IS IN CENTER OF MASS SYSTEM. 2000 1451 282 SECTION 65 THROUGH 73 2000 1451 283 ASSUMED ISOTROPIC(EACH SECTION REPRESENTS A GROUP OF LEVELS). 2000 1451 284 SECTION 91 INELASTIC SCATERING EXCITING THE CONTINUUM 2000 1451 285 ASSUMED ISOTROPIC IN THE CENTER OF MASS FRAME. 2000 1451 286 FILE 5 ENERGY DISTRIBUTION OF SECONDARY NEUTRONS 2000 1451 287 SECTION 16 (N,2N) REACTION 2000 1451 288 MAXWELLIAN DISTRIBUTIONS WITH TEMPERATURES DERIVED FROM 2000 1451 289 LEVEL DENSITIES AND LE COUTEUR THEORY. 2000 1451 290 SECTION 22 (N,NA) REACTION 2000 1451 291 TABULATED FROM CALCULATION. 2000 1451 292 SECTION 28 (N,NP) REACTION 2000 1451 293 TABULATED FROM CALCULATION. 2000 1451 294 SECTION 91 INELASTIC SCATERING EXCITING THE CONTINUUM 2000 1451 295 TABULATED FROM CALCULATION. 2000 1451 296 FILE 12 MULTIPLICITIES OF GAMMA RAYS PRODUCED BY NEUTRON REACTION 2000 1451 297 SECTION 4 TOTAL INELASTIC SCATTERING 2000 1451 298 BASED ON CALCULATED GAMMA-RAY SPECTRA. GOOD AGREEMENT 2000 1451 299 WITH EXPERIMENT. THE 1.158 MEV GAMMA-RAY FROM CA-44 IS 2000 1451 300 PARTIALLY BASED ON EXPERIMENTAL DATA AND IS TREATED AS A 2000 1451 301 DISCRETE PHOTON. 2000 1451 302 SECTION 22 (N,NA) REACTION 2000 1451 303 BASED ON CALCULATED GAMMA-RAY SPECTRA. 2000 1451 304 SECTION 28 (N,NP) REACTION 2000 1451 305 BASED ON CALCULATED GAMMA-RAY SPECTRA. 2000 1451 306 SECTION 102 RADIATIVE CAPTURE 2000 1451 307 ONLY GAMMA-RAYS FROM THERMAL-NEUTRON CAPTURE ARE INCLUDED. 2000 1451 308 SPECTRUM IS CONSTRUCTED FROM THE DECAY SCHEME PROPOSED BY 2000 1451 309 H. GRUPPELAAR AND P. SPILLING--NP A102(1967)226. 2000 1451 310 SECTION 103 (N,P) REACTION 2000 1451 311 CALCULATION FITTING EXPERIMENTAL DATA. 2000 1451 312 SECTION 107 (N,A) REACTION 2000 1451 313 CALCULATION FITTING EXPERIMENTAL DATA. 2000 1451 314 FILE 14 ANGULAR DISTRIBUTIONS OF SECONDARY GAMMA RAYS 2000 1451 315 ASSUMED ISOTROPIC IN THE CENTER OF MASS FRAME. 2000 1451 316 FILE 15 ENERGY DISTRIBUTION OF SECONDARY GAMMA RAYS 2000 1451 317 SEE FILE 12. 2000 1451 318 ******************************************************************2000 1451 319 2000 1451 320 DNA LIBRARY MATERIAL 4152 MOD 2 -- 2000 1451 321 Complete results of ORNL re-evaluation, May 1972. 2000 1451 322 2000 1451 323 ******************************************************************2000 1451 324 2000 1451 325 ENDF/B III Evaluation (Material 1152) Aug. 1971, F.G. Perey and 2000 1451 326 C.Y. Fu (ORNL) 2000 1451 327 2000 1451 328 DNA LIBRARY MATERIAL 4152 -- MOD 1. Same as ENDF/B III 1152. 2000 1451 329 Interim results of a complete re-evaluation at ORNL were 2000 1451 330 merged with MAT 540. 2000 1451 331 2000 1451 332 Historical Sketch----- 2000 1451 333 Material 540 -- Evaluated by M.K. Drake [Dr67]. 2000 1451 334 Translated into ENDF format by D.J. Dudziak (LASL), July 1969. 2000 1451 335 Revised by P.G. Young (LASL), May 1970. 2000 1451 336 2000 1451 337 **************************************************************** 2000 1451 338 2000 1451 339 REFERENCES 2000 1451 340 2000 1451 341 [Al75] B.J. Allen et al., Nuclear Cross Sections and Technology, 2000 1451 342 Proc. Conf.,Washington, DC, March 1975 [NBS Special 2000 1451 343 Publication 425], Vol.I (1975) p.360 2000 1451 344 [Al87] R. Alarcon and J. Rapaport, Nucl.Phys. A462, 445 (1987) 2000 1451 345 [Be69] F.D. Becchetti, Jr., and G.W. Greenlees, Phys.Rev. 182, 2000 1451 346 1190 (1969) 2000 1451 347 [Ch95] M.B. Chadwick, Lawrence Livermore National Laboratory 2000 1451 348 report UCRL-ID-122753 (1995) 2000 1451 349 [Ch96a] M.B. Chadwick, P.G. Young, R.E. MacFarlane, and A.J. 2000 1451 350 Koning, "High-Energy Nuclear Data Libraries for Accelerator- 2000 1451 351 Driven Technologies: Calculational Method for Heavy Recoils," 2000 1451 352 Proc. of 2nd Int. Conf. on Accelerator Driven Transmutation 2000 1451 353 Technology and Applications, Kalmar, Sweden, 3-7 June 1996. 2000 1451 354 [Ch96b] M.B. Chadwick and P.G. Young, Los Alamos National 2000 1451 355 Laboratory report LA-UR-96-0498 (1996) 2000 1451 356 [Ch97] M.B. Chadwick and P.G. Young, "GNASH Calculations of 2000 1451 357 n,p + 40Ca and Benchmarking of Results" in APT PROGRESS REPORT:2000 1451 358 1 February - 1 March 1997, internal Los Alamos National 2000 1451 359 Laboratory memo T-2-97/M-10, 7 Mar. 1997 from R.E. MacFarlane 2000 1451 360 to L. Waters. 2000 1451 361 [Ch99] M.B. Chadwick, P G. Young, G. M. Hale, et al., Los Alamos 2000 1451 362 National Laboratory report, LA-UR-99-1222 (1999) 2000 1451 363 [Cv67] Cvelbar et al., report NIJS-R-505 (1967) 2000 1451 364 [Di74] J.K. Dickens et al., Nucl.Sci.Eng., 53, 277 (1974) 2000 1451 365 [Dr67] M.K. Drake, Gulf General Atomic report GA-7829, Part 4 2000 1451 366 (1967) 2000 1451 367 [Fi93] R.W. Finley, W.P. Abfalterer, G. Fink, et al., Phys.Rev. 2000 1451 368 C 47, 237 (1993) 2000 1451 369 [Fr01] S.C. Frankle, R.C. Reedy, and P.G. Young, Los ALamos 2000 1451 370 National Laboratory Report, LA-13812 (2001). 2000 1451 371 [Fu76] C.Y. Fu, At.Data and Nucl.Data Tables 17, 127 (1976) 2000 1451 372 [Fu91] C.Y. Fu and D.M. Hetrick, Evaluation of neutron cross 2000 1451 373 sections of Ca for Release 0 of ENDF/B-VI, 1991. 2000 1451 374 [Ga76] D.I. Garber and R.R. Kinsey, report BNL-325, 3rd Ed., 2000 1451 375 Vol.II (1976) 2000 1451 376 [Ho86] G.M. Honore et al., Phys.Rev. C 33, 1129 (1986) 2000 1451 377 [Ig75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov.J. 2000 1451 378 Nucl.Phys. 21, 255 (1975); translation of Yad.Fiz. 21, 485 2000 1451 379 (1975) 2000 1451 380 [Is88] M.S. Islam, R.W. Finlay, J.S. Petler, et al., Phys.Med. 2000 1451 381 Biol. 33, 315 (1988) 2000 1451 382 [Ka88] C. Kalbach, Phys.Rev. C 37, 2350 (1988); see also 2000 1451 383 C. Kalbach and F.M. Mann, Phys.Rev. C 23, 112 (1981) 2000 1451 384 [Ko90] J. Kopecky and M. Uhl, Phys.Rev. C 41, 1941 (1990) 2000 1451 385 [Ma88] D.G. Madland, Proc. OECD/NEANDC Specialist's Mtg. on 2000 1451 386 Preequilibrium Nuclear Reactions, Semmering, Austria, Feb. 2000 1451 387 1988, NEANDC-245 'U' (1988) p.103 2000 1451 388 [Mu76] A.R. De L. Musgrove et al., Nucl.Phys. A259, 365 (1976) 2000 1451 389 [Pe63] C.M. Perey and F.G. Perey, Phys.Rev. 132, 755 (1963) 2000 1451 390 [Si74] U.N. Singh et al., Phys.Rev. C 10, 2143 (1974) 2000 1451 391 [Wi64] D. Wilmore and P.E. Hodgson, Nucl.Phys. 55, 673 (1964) 2000 1451 392 [Yo92] P.G. Young, E.D. Arthur, and M.B. Chadwick, report 2000 1451 393 LA-12343-MS (1992) 2000 1451 394 2000 1451 395 ************************ C O N T E N T S *********************** 2000 1451 396 ***************** Program LINEAR (VERSION 2004-1) ***************2000 1451 397 For All Data Greater than 1.0000E-10 barns in Absolute Value 2000 1451 398 Data Linearized to Within an Accuracy of .100000000 per-cent 2000 1451 399 ***************** Program FIXUP (Version 2004-1) ****************2000 1451 400 Corrected ZA/AWR in All Sections-----------------------------Yes 2000 1451 401 Corrected Thresholds-----------------------------------------No 2000 1451 402 Extended Cross Sections to 20 MeV----------------------------No 2000 1451 403 Allow Cross Section Deletion---------------------------------No 2000 1451 404 Allow Cross Section Reconstruction---------------------------Yes 2000 1451 405 Make All Cross Sections Non-Negative-------------------------Yes 2000 1451 406 Delete Energies Not in Ascending Order-----------------------Yes 2000 1451 407 Deleted Duplicate Points-------------------------------------Yes 2000 1451 408 Check for Ascending MAT/MF/MT Order--------------------------Yes 2000 1451 409 Check for Legal MF/MT Numbers--------------------------------Yes 2000 1451 410 Allow Creation of Missing Sections---------------------------No 2000 1451 411 Allow Insertion of Energy Points-----------------------------No 2000 1451 412 Create Uniform Energy Grid-----------------------------------No 2000 1451 413 Delete Section if Cross Section =0 at All Energies-----------Yes 2000 1451 414 **************** Program DICTIN (VERSION 2004-1) ****************2000 1451 415 1 451 501 22000 1451 416 2 151 4 02000 1451 417 3 1 1058 12000 1451 418 3 2 612 12000 1451 419 3 3 460 12000 1451 420 3 4 33 02000 1451 421 3 5 11 12000 1451 422 3 16 9 02000 1451 423 3 22 46 02000 1451 424 3 28 43 02000 1451 425 3 51 7 02000 1451 426 3 52 12 02000 1451 427 3 53 11 02000 1451 428 3 54 10 02000 1451 429 3 55 10 02000 1451 430 3 56 10 02000 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