24-Cr- 52 ENDF/B-VI, Processed by Red Cullen using PREPRO2004 6000 0 0 0 2.40520E+4 5.14940E+1 2 0 0 42431 1451 1 0.0 0.0 0 0 0 62431 1451 2 1.00000E+0 1.50000E+8 8 0 10 62431 1451 3 0.0 0.0 1 0 466 862431 1451 4 24-Cr- 52 LANL,ORNL EVAL-OCT97 S.CHIBA,M.CHADWICK,D.HETRICK 2431 1451 5 Ch97,Ch99 DIST-SEP 1 REV3- 20010926 2431 1451 6 ----ENDF/B-VI MATERIAL 2431 REVISION 2 2431 1451 7 -----INCIDENT NEUTRON DATA 2431 1451 8 ------ENDF-6 FORMAT 2431 1451 9 2431 1451 10 ******************************************************************2431 1451 11 2431 1451 12 ENDF/B-VI MOD 4 Revision, June 2000, S.C. Frankle, R.C. Reedy, 2431 1451 13 P.G. Young (LANL) 2431 1451 14 2431 1451 15 The secondary gamma-ray spectrum for radiative capture (MF 12, 2431 1451 16 MT 102) has been updated for new experimental data at incident 2431 1451 17 neutron energies up to 1 keV. 2431 1451 18 The previous (MOD 3) pure continuum at thermal neutron energy 2431 1451 19 is replaced by 11 discrete photons. 2431 1451 20 The MF=12, MT=102 yields from 1-100 keV were adjusted slightly 2431 1451 21 to force energy conservation. 2431 1451 22 The Q-value for radiative capture was also updated in File 3. 2431 1451 23 Details of these changes are described in Frankel et al. [Fr01]. 2431 1451 24 2431 1451 25 **************************************************************** 2431 1451 26 2431 1451 27 ENDF/B-VI MOD 3 Evaluation, October 1997, S. Chiba, M.B. Chadwick2431 1451 28 and P.G. Young (LANL) 2431 1451 29 2431 1451 30 Los Alamos LA150 Library, produced with FKK/GNASH/GSCAN code 2431 1451 31 in cooperation with ECN Petten. 2431 1451 32 2431 1451 33 This evaluation provides a complete representation of the 2431 1451 34 nuclear data needed for transport, damage, heating, 2431 1451 35 radioactivity, and shielding applications over the incident 2431 1451 36 neutron energy range from 1.0E-11 to 150 MeV. The discussion 2431 1451 37 here is divided into the region below and above 20 MeV. 2431 1451 38 2431 1451 39 INCIDENT NEUTRON ENERGIES < 20 MeV 2431 1451 40 2431 1451 41 Below 20 MeV the evaluation is based completely on the ENDF/B- 2431 1451 42 VI (Revision 1) evaluation by D. Hetrick, D. Larson, N. Larson, 2431 1451 43 and C. Y. Fu. 2431 1451 44 2431 1451 45 INCIDENT NEUTRON ENERGIES > 20 MeV 2431 1451 46 2431 1451 47 The ENDF/B-VI Release 2 evaluation extends to 20 MeV and 2431 1451 48 includes cross sections and energy-angle data for all 2431 1451 49 significant reactions. The present evaluation utilizes a more 2431 1451 50 compact composite reaction spectrum representation above 20 MeV 2431 1451 51 in order to reduce the length of the file. No essential data for 2431 1451 52 applications is lost with this representation. 2431 1451 53 The evaluation above 20 MeV utilizes MF=6, MT=5 to represent 2431 1451 54 all reaction data. Production cross sections and emission 2431 1451 55 spectra are given for neutrons, protons, deuterons, tritons, 2431 1451 56 alpha particles, gamma rays, and all residual nuclides produced 2431 1451 57 (A>5) in the reaction chains. To summarize, the ENDF sections 2431 1451 58 with non-zero data above En = 20 MeV are: 2431 1451 59 2431 1451 60 MF=3 MT= 1 Total Cross Section 2431 1451 61 MT= 2 Elastic Scattering Cross Section 2431 1451 62 MT= 3 Nonelastic Cross Section 2431 1451 63 MT= 5 Sum of Binary (n,n') and (n,x) Reactions 2431 1451 64 2431 1451 65 MF=4 MT= 2 Elastic Angular Distributions 2431 1451 66 2431 1451 67 MF=6 MT= 5 Production Cross Sections and Energy-Angle 2431 1451 68 Distributions for Emission Neutrons, Protons, 2431 1451 69 Deuterons, Tritons, and Alphas; and Angle- 2431 1451 70 Integrated Spectra for Gamma Rays and Residual 2431 1451 71 Nuclei That Are Stable Against Particle Emission 2431 1451 72 2431 1451 73 The evaluation is based on nuclear model calculations that 2431 1451 74 have been benchmarked to experimental data, especially for n + 2431 1451 75 Cr52 and p + Cr52 reactions [Ch97]. We use the GNASH code system 2431 1451 76 [Yo92], which utilizes Hauser-Feshbach statistical, 2431 1451 77 preequilibrium and direct-reaction theories. Spherical optical 2431 1451 78 model calculations are used to obtain particle transmission 2431 1451 79 coefficients for the Hauser-Feshbach calculations, as well as 2431 1451 80 for the elastic neutron angular distributions. 2431 1451 81 Cross sections and spectra for producing individual residual 2431 1451 82 nuclei are included for reactions. The energy-angle-correlations 2431 1451 83 for all outgoing particles are based on Kalbach systematics 2431 1451 84 [Ka88]. 2431 1451 85 A model was developed to calculate the energy distributions of 2431 1451 86 all recoil nuclei in the GNASH calculations [Ch96]. The recoil 2431 1451 87 energy distributions are represented in the laboratory system in 2431 1451 88 MT=5, MF=6, and are given as isotropic in the lab system. All 2431 1451 89 other data in MT=5,MF=6 are given in the center-of-mass system. 2431 1451 90 This method of representation utilizes the LCT=3 option approved 2431 1451 91 at the November, 1996, CSEWG meeting. 2431 1451 92 Preequilibrium corrections were performed in the course of the 2431 1451 93 GNASH calculations using the exciton model of Kalbach [Ka77, 2431 1451 94 Ka85], validated by comparison with calculations using Feshbach, 2431 1451 95 Kerman, Koonin (FKK) theory [Ch93]. Discrete level data from 2431 1451 96 nuclear data sheets were matched to continuum level densities 2431 1451 97 using the formulation of Ignatyuk et al. [Ig75] and pairing and 2431 1451 98 shell parameters from the Cook [Co67] analysis. Neutron and 2431 1451 99 charged- particle transmission coefficients were obtained from 2431 1451 100 the optical potentials, as discussed below. Gamma-ray 2431 1451 101 transmission coefficients were calculated using the Kopecky-Uhl 2431 1451 102 model [Ko90]. 2431 1451 103 2431 1451 104 SOME Cr-SPECIFIC INFORMATION CONCERNING THIS EVALUATION 2431 1451 105 The neutron total cross section was evaluated at grid energy 2431 1451 106 points by using the least-squares code GMA [Po81] taking 2431 1451 107 account of the new data measured by Dietrich et al. for 2431 1451 108 natural Cr[Di97]. The results were transformed to the Cr-52 2431 1451 109 cross section according to A*(2/3) law, i.e., by multiplying a 2431 1451 110 factor of 0.999305. 2431 1451 111 2431 1451 112 The evaluated total cross section data (present result from 20 2431 1451 113 to 250 MeV, and ENDF/B-VI value below 20 MeV), s-wave 2431 1451 114 strength function[Mu81], and elastic scattering angular 2431 1451 115 distribution data [Ki74, Ol87] were used to obtain the neutron 2431 1451 116 optical potential parameters. The parameter estimation was 2431 1451 117 carried out based on Bayesian approach [Sm91], where ECIS95 2431 1451 118 code was used for the optical model calculation. We have 2431 1451 119 employed the energy dependence of the optical potential 2431 1451 120 similar to Delaroche's work[De89]. Total of 18 parameters 2431 1451 121 concerning the central potential were estimated. 2431 1451 122 Presently obtained potential was used for the 2431 1451 123 calculation of neutron transmission coefficients and DWBA cross 2431 1451 124 sections in the entire energy region. 2431 1451 125 2431 1451 126 For proton channel, a combination of 2 potentials were 2431 1451 127 used : 2431 1451 128 below 40 MeV : Becchetti-Greenlees 2431 1451 129 above 40 MeV : Madland medium energy potential 2431 1451 130 2431 1451 131 The proton reaction cross section and transmission coefficients 2431 1451 132 below 40 MeV were multiplied by a factor of 0.845 to make the 2431 1451 133 agreement with the measured proton reaction cross section 2431 1451 134 [Ca96] better, and also to make the connection to higher energy 2431 1451 135 values smoothly. 2431 1451 136 For deuterons, the Lohr-Haeberli global potential was used; for 2431 1451 137 alpha particles the Moyen potential (MacFadden-Satchler) was 2431 1451 138 used; and for tritons the Becchetti-Greenlees potential was used. 2431 1451 139 The He-3 channelwas ignored. 2431 1451 140 The direct collective inelastic scattering to the following 2431 1451 141 levels in Cr-52 was considered by the DWBA-mode calculation 2431 1451 142 of ECIS95: 2431 1451 143 Jpi Ex(MeV) Deformation length 2431 1451 144 2+ 1.434 0.87 2431 1451 145 4+ 2.369 0.33 2431 1451 146 0+ 2.647 0.095 2431 1451 147 4+ 2.768 0.30 2431 1451 148 2+ 2.965 0.08 2431 1451 149 6+ 3.114 0.35 2431 1451 150 2+ 3.162 0.27 2431 1451 151 4+ 3.415 0.13 2431 1451 152 2+ 3.772 0.28 2431 1451 153 4+ 4.040 0.16 2431 1451 154 3- 4.563 0.61 2431 1451 155 4+ 4.630 0.36 2431 1451 156 0+ 4.738 0.145 2431 1451 157 4+ 4.951 0.20 2431 1451 158 4+ 5.095 0.15 2431 1451 159 4+ 5.425 0.32 2431 1451 160 4+ 5.541 0.074 2431 1451 161 2+ 5.661 0.095 2431 1451 162 3- 5.873 0.082 2431 1451 163 3- 5.996 0.087 2431 1451 164 2+ 6.055 0.13 2431 1451 165 2+ 6.143 0.07 2431 1451 166 2+ 6.175 0.21 2431 1451 167 2+ 6.493 0.21 2431 1451 168 3- 6.580 0.34 2431 1451 169 3- 6.786 0.26 2431 1451 170 2+ 6.810 0.22 2431 1451 171 5- 6.871 0.16 2431 1451 172 3- 6.993 0.18 2431 1451 173 3- 7.080 0.34 2431 1451 174 4+ 7.140 0.14 2431 1451 175 2+ 7.217 0.10 2431 1451 176 4+ 7.278 0.13 2431 1451 177 2+ 7.344 0.074 2431 1451 178 5- 7.376 0.11 2431 1451 179 3- 7.409 0.091 2431 1451 180 3- 7.482 0.13 2431 1451 181 3- 7.585 0.074 2431 1451 182 3- 7.738 0.26 2431 1451 183 3- 7.823 0.12 2431 1451 184 4+ 7.848 0.11 2431 1451 185 4+ 7.893 0.12 2431 1451 186 3- 7.967 0.095 2431 1451 187 2+ 8.022 0.10 2431 1451 188 3- 8.089 0.091 2431 1451 189 3- 8.281 0.15 2431 1451 190 3- 8.457 0.13 2431 1451 191 3- 8.505 0.10 2431 1451 192 3- 8.679 0.10 2431 1451 193 3- 8.782 0.10 2431 1451 194 3- 8.778 0.13 2431 1451 195 3- 9.440 0.095 2431 1451 196 2431 1451 197 These data were retrieved from the literature [Ju94]. 2431 1451 198 2431 1451 199 *************************************************************** 2431 1451 200 2431 1451 201 ENDF/B-VI MOD 2 Revision, July 1991, D. Hetrick, D. Larson, 2431 1451 202 N. Larson, and C. Y. Fu (ORNL) 2431 1451 203 2431 1451 204 Revision 1 changes 2431 1451 205 The elastic transformation matrix was removed. 2431 1451 206 2431 1451 207 **************************************************************** 2431 1451 208 2431 1451 209 ENDF/B-VI MOD 1 Evaluation, November 1989, D. Larson (ORNL) 2431 1451 210 2431 1451 211 This work employed nuclear model codes including the 2431 1451 212 Distorted Wave Born Approximation (DWBA) program DWUCK [Ku72] 2431 1451 213 and the Hauser-Feshbach code TNG [Fu80,Fu88,Sh86]. The TNG code 2431 1451 214 provides energy and angular distributions of particles emitted 2431 1451 215 in the compound and pre-compound reactions, ensures consistency 2431 1451 216 among all reactions, and maintains energy balance. Details 2431 1451 217 pertinent to the contents of this evaluation and extensive 2431 1451 218 comparisons of calculations with experimental data can be found 2431 1451 219 in Hetrick [He87]. 2431 1451 220 2431 1451 221 DESCRIPTION OF FILES 2431 1451 222 (MF-MT) 2431 1451 223 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2431 1451 224 2-151 RESONANCE PARAMETERS; USED TO PROVIDE THE TOTAL AND 2431 1451 225 SCATTERING CROSS SECTIONS FROM 1.E-5 EV TO 980 KEV, AND 2431 1451 226 CAPTURE FROM 1.E-5 TO 375 KEV. A SMALL CONTRIBUTION IN 2431 1451 227 3-102 IS ADDED TO 2-151 FOR CAPTURE FROM 375 TO 980 KEV 2431 1451 228 (SEE 3-102 BELOW). THE RESONANCE PARAMETERS 2431 1451 229 FROM [Br85] (WITH HELP FROM BRUSEGAN ET AL. (PRIVATE 2431 1451 230 COMM., 1988)) WERE ADJUSTED TO MINIMIZE DIFFERENCE WITH 2431 1451 231 DATA OF REF. [Ag84]. 2431 1451 232 NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2431 1451 233 OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE 2431 1451 234 PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON 2431 1451 235 A FINER ENERGY GRID THAN GIVEN IN 4/2. 2431 1451 236 3-1 TOTAL CROSS SECTION; GIVEN BY RESONANCE PARAMETERS UP TO 2431 1451 237 980 KEV WITH NEGATIVE ENERGY RESONANCES ADJUSTED TO GIVE 2431 1451 238 MEASURED THERMAL SCATTERING AND CAPTURE CROSS SECTIONS 2431 1451 239 (SEE 3-102 BELOW). FROM 20 - 980 KEV A BACKGROUND FILE 2431 1451 240 IS REQUIRED. FROM 980 KEV TO 20.0 MEV, HIGH 2431 1451 241 RESOLUTION NAT CR TRANSMISSION MEASUREMENTS WERE USED 2431 1451 242 D.C. LARSON, J.A. HARVEY, AND N.W. HILL, PRIVATE COMM., 2431 1451 243 1988; DATA AVAILABLE AT NNDC) RATHER THAN LOWER 2431 1451 244 RESOLUTION ISOTOPIC DATA. 2431 1451 245 3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY 2431 1451 246 SUBTRACTING THE NONELASTIC FROM THE TOTAL 2431 1451 247 3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22, 2431 1451 248 3-28, 3-102, 3-103, AND 3-107. 2431 1451 249 3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, .. 2431 1451 250 .., 3-60, AND 3-91 2431 1451 251 3-16 (N,2N) CROSS SECTIONS WERE TAKEN FROM THE ACTIVATION 2431 1451 252 FILE FOR 52CR BUT WERE ADJUSTED TO BE SMALLER 2431 1451 253 BELOW ENERGY OF 15.5 MEV TO MATCH THE DATA 2431 1451 254 OF WAGNER ET AL. [Wa88] WHICH AGREES WELL WITH OTHER 2431 1451 255 DATA IN THIS ENERGY REGION. 2431 1451 256 3-22 (N,NA) CROSS SECTIONS WERE CALCULATED BY THE TNG CODE 2431 1451 257 [Fu80,Fu88,Sh86]. NO DATA AVAILABLE OTHER THAN A-EMISSION2431 1451 258 3-28 (N,NP) CROSS SECTIONS WERE CALCULATED BY THE TNG CODE 2431 1451 259 [Fu80,Fu88,Sh86]. NO DATA AVAILABLE OTHER THAN P-EMISSION2431 1451 260 3-51 TO 3-60 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE 2431 1451 261 FROM TNG [Fu80,Fu88,Sh86] WHICH INCLUDES DIRECT 2431 1451 262 INTERACTION CROSS SECTIONS FROM DWUCK [Ku72] CALCULATIONS.2431 1451 263 COMPARISONS WITH EXPERIMENTAL DATA USED IN THE EVALUATION2431 1451 264 PROCESS ARE SHOWN IN [He87]. 2431 1451 265 3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM (TNG 2431 1451 266 CALCULATED). GUIDANCE FROM (N,XN) EMISSION DATA [He87]. 2431 1451 267 3-102 (N,G) CAPTURE CROSS SECTION; GIVEN BY RESONANCE PARAMETERS2431 1451 268 UP TO 980 KEV AND FROM 980 KEV TO 20 MEV, TNG CALC'S 2431 1451 269 WERE USED BUT NORMALIZED TO MEASURED AVE. CAPTURE BETWEEN 2431 1451 270 100 KEV AND 1.0 MEV. A SMALL CONTIBUTION TO BE ADDED TO 2431 1451 271 2-151 IS GIVEN FROM 375-980 KEV DUE TO INCOMPLETE 2431 1451 272 CAPTURE RESONANCE INFORMATION. TNG CALCULATIONS INCLUDED 2431 1451 273 A PRECOMPOUND COMPONENT AND WEIGHTED CROSS SECTIONS FROM 2431 1451 274 ISOTOPES OF CR GIVE 0.82 MB AT 14.5 MEV, IN AGREEMENT WITH2431 1451 275 THE MEASUREMENT OF 0.75 MB FOR NAT CR. 2431 1451 276 3-103 (N,P) CROSS SECTIONS WERE CALCULATED BY THE TNG CODE 2431 1451 277 [Fu80,Fu88,Sh86], BUT MODIFIED BETWEEN 7 TO 16 MEV TO 2431 1451 278 BETTER FIT THE DATA OF SMITH ET AL. [Sm80] UP TO 9 MEV AND2431 1451 279 RECENT MEASUREMENTS AT 14.5 MEV [Gu85,Ar80,Mo77]. 2431 1451 280 3-107 (N,A) CROSS SECTIONS WERE CALCULATED BY THE TNG CODE 2431 1451 281 [Fu80,Fu88,Sh86]. NO DATA AVAILABLE OTHER THAN A-EMISSION.2431 1451 282 4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR 2431 1451 283 ELASTIC SCATTERING ARE FROM ENDF/B-V. 2431 1451 284 IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY 2431 1451 285 THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE 2431 1451 286 PARAMETERS IN 2/151. 2431 1451 287 6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2431 1451 288 NEUTRON AND 51CR RESIDUAL, AND ENERGY DEPENDENT YIELD 2431 1451 289 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2431 1451 290 RAY; TNG CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR2431 1451 291 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2431 1451 292 THE OUTGOING NEUTRON). (N,XN) D-D EMISSION DATA HEAVILY 2431 1451 293 USED TO BENCHMARK THE TNG CALCULATIONS [He87]. 2431 1451 294 6-22 (N,NA) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2431 1451 295 NEUTRON, ALPHA, AND 48TI RESIDUAL, AND ENERGY DEPENDENT 2431 1451 296 YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE 2431 1451 297 GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2431 1451 298 FOR EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY 2431 1451 299 FOR THE OUTGOING NEUTRON; ISOTROPY IS ASSUMED FOR THE 2431 1451 300 ALPHA AND RESIDUAL). (N,XA) D-D EMISSION DATA HEAVILY 2431 1451 301 USED TO BENCHMARK THE CALCULATIONS [He87]. 2431 1451 302 6-28 (N,NP) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE 2431 1451 303 NEUTRON AND 51V RESIDUAL, AND ENERGY DEPENDENT YIELD 2431 1451 304 BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA 2431 1451 305 RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR 2431 1451 306 EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR 2431 1451 307 THE OUTGOING NEUTRON). (N,XP) D-D EMISSION DATA HEAVILY 2431 1451 308 USED TO BENCHMARK THE CALCULATIONS [He87]. 2431 1451 309 6-51 THROUGH 6-60 INELASTIC SCATTERING EXCITING LEVELS; EACH 2431 1451 310 SECTION INCLUDES SIMPLE CONSTANT YIELDS FOR THE NEUTRON 2431 1451 311 AND 52CR RESIDUAL; ANGULAR DISTRIBUTIONS ARE GIVEN FOR 2431 1451 312 THE OUTGOING NEUTRON (LEGENDRE COEFFICIENTS COMPUTED 2431 1451 313 BY DWUCK [Ku72] AND TNG [Fu80,Fu88,Sh86]. COMPARISONS 2431 1451 314 WITH ANGULAR DISTRIBUTION DATA ARE GIVEN IN [He87]. 2431 1451 315 6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES 2431 1451 316 SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 52CR 2431 1451 317 RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG 2431 1451 318 CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; TNG 2431 1451 319 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN 2431 1451 320 FOR EACH (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR THE 2431 1451 321 OUTGOING NEUTRON). (N,XN) D-D EMISSION DATA HEAVILY USED 2431 1451 322 TO BENCHMARK THE TNG CALCULATIONS [He87]. 2431 1451 323 6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P 2431 1451 324 AND 52V RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2431 1451 325 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2431 1451 326 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2431 1451 327 PRODUCT. (N,XP) D-D EMISSION DATA USED TO BENCHMARK 2431 1451 328 THE TNG CALCULATIONS [He87]. 2431 1451 329 6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A 2431 1451 330 AND 49TI RESIDUAL, AND ENERGY DEPENDENT YIELD BASED 2431 1451 331 ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; 2431 1451 332 CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH 2431 1451 333 PRODUCT. (N,XA) D-D EMISSION DATA USED TO BENCHMARK 2431 1451 334 THE TNG CALCULATIONS [He87]. 2431 1451 335 12-51 THROUGH 12-60 BRANCHING RATIOS FOR THE LEVELS, COMPILED 2431 1451 336 BY HETRICK ET AL. [He87], ARE GIVEN. 2431 1451 337 12-102 (N,G) CAPTURE; TNG CALCULATED. 2431 1451 338 14-51 THROUGH 14-58 AND 14-102 GAMMA RAY ANGULAR DISTRIBUTIONS 2431 1451 339 ASSUMED TO BE ISOTROPIC. 2431 1451 340 15-102 (N,G) CAPTURE; TNG CALCULATED. 2431 1451 341 2431 1451 342 ---------------------------------------------------------------- 2431 1451 343 UNCERTAINTY FILES 2431 1451 344 AN LB=8 SECTION IS INCLUDED FOR ALL NON-DERIVED FILES AS 2431 1451 345 REQUIRED BY ENDF/B-VI. 2431 1451 346 2431 1451 347 33-1 UNCERTAINTIES ARE DERIVED FROM 1.E-5 TO 100 EV. FROM 100 2431 1451 348 EV TO 20 MEV THEY ARE EXPLICIT, USING LB=0,1 AND 8. 2431 1451 349 33-2 FROM 1.E-5 TO 100 EV, UNCERTAINTIES ARE EXPLICIT, BASED 2431 1451 350 UPON THERMAL UNCERTAINTY AND OTHER DATA. FROM 100 EV TO 2431 1451 351 20 MEV THE FILES ARE DERIVED. 2431 1451 352 33-3 FROM 1.E-5 TO 980 KEV UNCERTAINTIES ARE DERIVED. FROM 9802431 1451 353 KEV TO 20 MEV UNCERTAINTIES ARE EXPLICIT, USING LB=1 AND 82431 1451 354 33-4 UNCERTAINTIES ARE ALL DERIVED. 2431 1451 355 33-16 UNCERTAINTIES FOR (N,2N) ARE EXPLICIT, CSISRS DATA USED 2431 1451 356 AS A GUIDE. 2431 1451 357 33-22 UNCERTAINTIES FOR (N,NA) ARE EXPLICIT, ESTIMATED FROM TNG 2431 1451 358 33-28 UNCERTAINTIES FOR (N,NP) ARE EXPLICIT, ESTIMATED FROM TNG 2431 1451 359 33-51-91 UNCERTAINTIES FOR INELASTIC SCATTERING ARE EXPLICIT, 2431 1451 360 BASED ON DATA AND CALCULATION UNCERTAINTIES. 2431 1451 361 33-102 UNCERTAINTIES ARE EXPLICIT, BASED ON THERMAL DATA AT LOW 2431 1451 362 ENERGIES, AND CALCULATED RESULTS ABOVE 980 KEV. 2431 1451 363 33-103 UNCERTAINTIES ESTIMATED FROM TNG. 2431 1451 364 33-107 UNCERTAINTIES ESTIMATED FROM TNG. 2431 1451 365 2431 1451 366 *************************************************************** 2431 1451 367 2431 1451 368 REFERENCES 2431 1451 369 2431 1451 370 [Ag84] H.M. Agrawal, J.B. Garg and J.A. Harvey, Phys.Rev. C 30, 2431 1451 371 1880 (1984) 2431 1451 372 [Ar80] Artem'ev et al., At.En. 49, 195 (1980) 2431 1451 373 [Be69] F.D. Becchetti, Jr., and G.W. Greenlees, Phys. Rev. 2431 1451 374 182, 1190 (1969) 2431 1451 375 [Be71] F.D. Becchetti, Jr., and G.W. Greenlees, Polarization 2431 1451 376 Phenomena in Nuclear Reactions, Proc. Conf. (Ed: H.H. 2431 1451 377 Barschall and W. Haeberli, The University of Wisconsin Press, 2431 1451 378 1971) p.682 2431 1451 379 [Br85] A. Brusegan, R. Buyl, F.Corvi et al., Nuclear Data for 2431 1451 380 Basic and Applied Science, Proc. Conf. Santa Fe, NM, May 1985 2431 1451 381 (Gordon and Breach, 1986) p.633 2431 1451 382 [Bu95] T.W. Burrows, Nucl.Data Sheets, 75, 1 (1995) 2431 1451 383 [Ca96] R.F. Carlson, Atomic Data and Nuclear Data Tables, 63, 2431 1451 384 93 (1996) 2431 1451 385 [Ch93] M.B. Chadwick and P.G. Young, Phys.Rev. C 47, 2255 (1993) 2431 1451 386 [Ch96] M.B. Chadwick, P.G. Young, R.E. MacFarlane, and A.J. 2431 1451 387 Koning, "High-Energy Nuclear Data Libraries for Accelerator- 2431 1451 388 Driven Technologies: Calculational Method for Heavy Recoils," 2431 1451 389 Proc. of 2nd Int. Conf. on Accelerator Driven Transmutation 2431 1451 390 Technology and Applications, Kalmar, Sweden, 3-7 June 1996. 2431 1451 391 [Ch97] M.B. Chadwick and P.G. Young, "Model Calculations of 2431 1451 392 n,p + 58,60,61,62,64Ni" in APT PROGRESS REPORT: 1 August - 1 2431 1451 393 September 1997, internal Los Alamos National Laboratory memo T-2431 1451 394 2-97/MS-51, 8 September 1997 from R.E. MacFarlane to L. Waters.2431 1451 395 [Ch99] M.B. Chadwick, P G. Young, G. M. Hale, et al., Los Alamos 2431 1451 396 National Laboratory report, LA-UR-99-1222 (1999) 2431 1451 397 [Co67] J.L. Cook, H. Ferguson, and A.R. De L Musgrove, Aust.J. 2431 1451 398 Phys. 20, 477 (1967) 2431 1451 399 [De89] J.P. Delaroche, Y. Wang and J. Rapaport, Phys.Rev. C 39, 2431 1451 400 391 (1989) 2431 1451 401 [Di97] F. Dietrich et al., private communication (1997) 2431 1451 402 [Fr01] S.C. Frankle, R.C. Reedy, and P.G. Young, Los ALamos 2431 1451 403 National Laboratory Report, LA-13812 (2001). 2431 1451 404 [Fu80] C.Y Fu, Symp. on Neutron Cross Sections from 10 to 50 MeV,2431 1451 405 Upton, NY, May 1980, Brookhaven National Lab. report 2431 1451 406 BNL-NCS-51425 (1980) p.675 2431 1451 407 [Fu88] C.Y. Fu, report ORNL/TM-7042 (1980) and Nucl.Ssci.Eng. 2431 1451 408 100, 61 (1988) 2431 1451 409 [Gu85] Gupta et al., J.Phys, India, 24, 637 (1985) 2431 1451 410 [He87] D.M. HETRICK, C.Y. FU, AND D.C. LARSON, report 2431 1451 411 ORNL/TM-10417 [ENDF-346] (1987) 2431 1451 412 [Ig75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov.J. 2431 1451 413 Nucl.Phys. 21, 255 (1975); translation of Yad.Fiz. 21, 485 2431 1451 414 (1975) 2431 1451 415 [Ka77] C. Kalbach, Z.Phys. A 283, 401 (1977) 2431 1451 416 [Ka85] C. Kalbach, Los Alamos National Laboratory report 2431 1451 417 LA-10248-MS (1985) 2431 1451 418 [Ka88] C. Kalbach, Phys.Rev. C 37, 2350 (1988); see also 2431 1451 419 C. Kalbach and F.M. Mann, Phys.Rev. C 23, 112 (1981) 2431 1451 420 [Ki74] W.E. Kinney et al., report ORNL-4806 (1974) 2431 1451 421 [Ko90] J. Kopecky and M. Uhl, Phys.Rev. C 41, 1941 (1990) 2431 1451 422 [Ku72] P.D. Kunz, "Distorted Wave Code DWUCK72," Univ. of 2431 1451 423 Colorado, unpublished (1972) 2431 1451 424 [Lo74] J.M. Lohr and W. Haeberli, Nucl.Phys. A232, 381 (1974) 2431 1451 425 [Mo77] N.I. Molla and S.M. Qaim, Nucl.Phys., A283, 269 (1977) 2431 1451 426 [Mu81] S.F. Mughabghab, M. Divadeenam and N.E. Holden, "Neutron 2431 1451 427 Cross Sections", Vol. 1, Part A, (Academic Press, 1981) 2431 1451 428 [Ol87] N. Olsson et al, Nucl.Phys. A472, 237 (1987) 2431 1451 429 [Po81] W. Poenitz, Proc. Conf. on Nuclear Data Evaluation Methods2431 1451 430 and Procedures, Brookhaven National Laboratory Report BNL-NCS- 2431 1451 431 51363 Vol.1 (1981) p.249 2431 1451 432 [Ra96] J. Raynal, "Notes on ECIS94", Service de Physique 2431 1451 433 Theorique, Saclay, France (personal communication through A. J.2431 1451 434 Koning, 1996). 2431 1451 435 [Sh86] K. Shibata and C.Y. Fu, report ORNL/TM-10093 (1986) 2431 1451 436 [Sm80] D.L. Smith and J.W. Meadows, Nucl.Sci.Eng. 76, 43 (1980) 2431 1451 437 [Sm91] D.L. Smith, "Probability, Statistics, and Data Uncertainty2431 1451 438 in Nuclear Science and Technology" (American Nuclear Society, 2431 1451 439 1991) 2431 1451 440 [Wa88] M. Wagner, G. Winkler, H. Liskien and R. Widera, 2431 1451 441 "Measurement of the excitation function for the 52Cr(n,2n)51Cr 2431 1451 442 reaction from 12.7 to 19.5 MeV," IRK progress report (1987/ 2431 1451 443 1988) 2431 1451 444 [Yo92] P.G. Young, E.D. Arthur, and M.B. Chadwick, report 2431 1451 445 LA-12343-MS (1992) 2431 1451 446 2431 1451 447 ************************ C O N T E N T S *********************** 2431 1451 448 ***************** Program LINEAR (VERSION 2004-1) ***************2431 1451 449 For All Data Greater than 1.0000E-10 barns in Absolute Value 2431 1451 450 Data Linearized to Within an Accuracy of .100000000 per-cent 2431 1451 451 ***************** Program RECENT (VERSION 2004-1) ***************2431 1451 452 for All Data Greater than 1.0000E-10 barns in Absolute Value 2431 1451 453 Data Linearized to within an Accuracy of .100000000 per-cent 2431 1451 454 ***************** Program FIXUP (Version 2004-1) ****************2431 1451 455 Corrected ZA/AWR in All Sections-----------------------------Yes 2431 1451 456 Corrected Thresholds-----------------------------------------No 2431 1451 457 Extended Cross Sections to 20 MeV----------------------------No 2431 1451 458 Allow Cross Section Deletion---------------------------------No 2431 1451 459 Allow Cross Section Reconstruction---------------------------Yes 2431 1451 460 Make All Cross Sections Non-Negative-------------------------Yes 2431 1451 461 Delete Energies Not in Ascending Order-----------------------Yes 2431 1451 462 Deleted Duplicate Points-------------------------------------Yes 2431 1451 463 Check for Ascending MAT/MF/MT Order--------------------------Yes 2431 1451 464 Check for Legal MF/MT Numbers--------------------------------Yes 2431 1451 465 Allow Creation of Missing Sections---------------------------No 2431 1451 466 Allow Insertion of Energy Points-----------------------------No 2431 1451 467 Create Uniform Energy Grid-----------------------------------No 2431 1451 468 Delete Section if Cross Section =0 at All Energies-----------Yes 2431 1451 469 **************** Program DICTIN (VERSION 2004-1) ****************2431 1451 470 1 451 556 42431 1451 471 2 151 230 12431 1451 472 3 1 21140 32431 1451 473 3 2 21122 32431 1451 474 3 3 19690 32431 1451 475 3 4 17 12431 1451 476 3 5 10 32431 1451 477 3 16 8 12431 1451 478 3 22 6 12431 1451 479 3 28 6 12431 1451 480 3 51 14 12431 1451 481 3 52 12 12431 1451 482 3 53 12 12431 1451 483 3 54 12 12431 1451 484 3 55 11 12431 1451 485 3 56 11 12431 1451 486 3 57 11 12431 1451 487 3 58 11 12431 1451 488 3 59 11 12431 1451 489 3 60 11 12431 1451 490 3 91 10 12431 1451 491 3 102 19672 42431 1451 492 3 103 11 12431 1451 493 3 107 11 12431 1451 494 4 2 4248 32431 1451 495 6 5 12608 32431 1451 496 6 16 262 12431 1451 497 6 22 276 12431 1451 498 6 28 335 12431 1451 499 6 51 47 12431 1451 500 6 52 44 12431 1451 501 6 53 7 12431 1451 502 6 54 41 12431 1451 503 6 55 41 12431 1451 504 6 56 41 12431 1451 505 6 57 44 12431 1451 506 6 58 7 12431 1451 507 6 59 7 12431 1451 508 6 60 7 12431 1451 509 6 91 1202 12431 1451 510 6 103 684 12431 1451 511 6 107 792 12431 1451 512 12 51 3 12431 1451 513 12 52 3 12431 1451 514 12 53 3 12431 1451 515 12 54 3 12431 1451 516 12 55 3 12431 1451 517 12 56 3 12431 1451 518 12 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