8-O - 16 ENDF/B-VI, Processed by Red Cullen using PREPRO2004 6000 0 0 0 8.01600E+3 1.58575E+1 0 0 0 3 825 1451 1 0.0 0.0 0 0 0 6 825 1451 2 1.00000E+0 3.00000E+7 8 0 10 6 825 1451 3 0.0 0.0 1 0 835 144 825 1451 4 8-O - 16 LANL EVAL-APR01 HALE,YOUNG,CHADWICK,CARO,LUBITZ 825 1451 5 Ch96ab,Ca98,Ch99,Yo01 DIST-SEP 1 REV2- 20011018 825 1451 6 ----ENDF/B-VI MATERIAL 825 825 1451 7 -----INCIDENT NEUTRON DATA 825 1451 8 ------ENDF-6 FORMAT 825 1451 9 825 1451 10 ****************************************************************** 825 1451 11 825 1451 12 ENDF/B-VI MOD 3 Evaluation, April 2001, P.G. Young, G.M. Hale 825 1451 13 M.B. Chadwick (LANL), E.Caro, C.R. Lubitz (KAPL) 825 1451 14 825 1451 15 This evaluation is a combination of a new MOD 3 evaluation 825 1451 16 below 30 MeV and the previous MOD 2 evaluation from 20 to 150 MeV. 825 1451 17 Both these evaluations are described below. The only change to the 825 1451 18 data above 30 MeV is to add tritium-production data, based on 825 1451 19 experimental yield data and spectra calculated with the GNASH 825 1451 20 Hauser-Feshbach/preequilibrium code. 825 1451 21 This evaluation provides a complete representation of the 825 1451 22 nuclear data needed for transport, damage, heating, radioactivity, 825 1451 23 and shielding applications over the incident neutron energy range 825 1451 24 from 1.0E-11 to 150 MeV. The discussion here is divided into the 825 1451 25 region above and below 30 MeV. 825 1451 26 825 1451 27 ------------------------------------------------------------------ 825 1451 28 825 1451 29 INCIDENT NEUTRON ENERGIES > 30 MeV 825 1451 30 825 1451 31 The evaluation above 30 MeV utilizes MF=6, MT=5 to represent 825 1451 32 all reaction data. Production cross sections and emission 825 1451 33 spectra are given for neutrons, protons, deuterons, alpha 825 1451 34 particles, gamma rays, and all residual nuclides produced (A>5) 825 1451 35 in the reaction chains. To summarize, the ENDF sections with 825 1451 36 non-zero data above En = 30 MeV are: 825 1451 37 825 1451 38 MF=3 MT= 1 Total Cross Section 825 1451 39 MT= 2 Elastic Scattering Cross Section 825 1451 40 MT= 3 Nonelastic Cross Section 825 1451 41 MT= 5 Sum of Binary (n,n') and (n,x) Reactions 825 1451 42 MT=102 Radiative Capture Cross Section (Estimate Only) 825 1451 43 825 1451 44 MF=4 MT= 2 Elastic Angular Distributions 825 1451 45 825 1451 46 MF=6 MT= 5 Production Cross Sections and Energy-Angle 825 1451 47 Distributions for Emission Neutrons, Protons, 825 1451 48 Deuterons, and Alphas; and Angle-Integrated 825 1451 49 Spectra for Gamma Rays and Residual Nuclei That 825 1451 50 Are Stable Against Particle Emission 825 1451 51 825 1451 52 The evaluation is based on nuclear model calculations that 825 1451 53 have been benchmarked to experimental data, especially for n + 825 1451 54 O16 and p + O16 reactions [Ch96a]. We use the GNASH code system 825 1451 55 [Yo92], which utilizes Hauser-Feshbach statistical, preequi- 825 1451 56 librium and direct-reaction theories. Coupled-channel and 825 1451 57 spherical optical model calculations are used to obtain particle 825 1451 58 transmission coefficients for the Hauser-Feshbach calculations, 825 1451 59 as well as for the elastic neutron angular distributions. 825 1451 60 Cross sections and spectra for producing individual residual 825 1451 61 nuclei are included for reactions that exceed a cross section of 825 1451 62 approximately 1 nb at any energy. The energy-angle-correlations 825 1451 63 for all outgoing particles are based on Kalbach systematics 825 1451 64 [Ka88]. 825 1451 65 A model was developed to calculate the energy distributions of 825 1451 66 all recoil nuclei in the GNASH calculations [Ch96b]. The recoil 825 1451 67 energy distributions are represented in the laboratory system in 825 1451 68 MT=5, MF=6, and are given as isotropic in the lab system. Note 825 1451 69 that all other data in MT=5,MF=6 are given in the center-of-mass 825 1451 70 system. This method of representation requires a modification of 825 1451 71 the original ENDF-6 format. 825 1451 72 Preequilibrium corrections were performed in the course of the 825 1451 73 GNASH calculations using either Feshbach, Kerman, Koonin (FKK) 825 1451 74 theory [Ch93] or the exciton model of Kalbach [Ka77, Ka85]. 825 1451 75 Discrete level data from nuclear data sheets were matched to 825 1451 76 continuum level densities using the formulation of Ignatyuk 825 1451 77 [Ig75] and pairing and shell parameters from the Cook [Co67] 825 1451 78 analysis. Neutron and charged-particle transmission coefficients 825 1451 79 were obtained from the optical potentials, as discussed below. 825 1451 80 Gamma-ray transmission coefficients were calculated using the 825 1451 81 Kopecky-Uhl model [Ko90]. 825 1451 82 825 1451 83 ------------------------------------------------------------------ 825 1451 84 825 1451 85 INCIDENT NEUTRON ENERGIES < 30 MeV 825 1451 86 825 1451 87 The evaluation below 30 MeV includes complete data for all 825 1451 88 significant neutron-induced reactions. It is comprised of 825 1451 89 R-parameter [Ca98] and R-matrix analyses below 6.25 MeV, and a 825 1451 90 combination of experimental and theoretical data evaluation 825 1451 91 from 6.25 to 30 MeV. A summary of the evaluation by energy 825 1451 92 range is given below, followed by a detailed description of 825 1451 93 the evaluation, reaction by reaction. 825 1451 94 825 1451 95 NEUTRON ENERGY < 6.25 MeV 825 1451 96 825 1451 97 The evaluation below 3.4 MeV is an R-function fit [Ca98] to 825 1451 98 experimental data. At 3.4 MeV, it is spliced to the LANL R-matrix 825 1451 99 analysis with a transition region of about 60 keV centered at 825 1451 100 3.4 MeV. The LANL analysis is used for the region from 3.40 to 825 1451 101 6.25 MeV. 825 1451 102 825 1451 103 NEUTRON ENERGY > 6.25 MeV 825 1451 104 825 1451 105 The following major modifications were made above 6.25 MeV: 825 1451 106 1. The maximum energy of the evaluation was increased from 20 to 825 1451 107 30 MeV. 825 1451 108 2. New measurements of 16O(n,xgamma) angular distributions (7 825 1451 109 angles, En = 4 - 200 MeV) by Nelson et al. [Ne99] were incor- 825 1451 110 porated into the evaluation. The measurements use a high- 825 1451 111 resolution Ge detector and result in data for some 21 gamma rays. 825 1451 112 The distributions were fit with Legendre expansions to obtain 825 1451 113 angle-integrated cross sections for MF=13 and angular 825 1451 114 distributions for MF=14. Nuclear energy level schemes and gamma 825 1451 115 branching ratios [Aj86,Aj91] were utilized to extract level 825 1451 116 excitation cross sections in MF=3 for discrete states in 16O, 825 1451 117 14-16N, and 13C, corresponding to (n,n'), (n,p), (n,d), (n,t), 825 1451 118 and (n,alpha) reactions. 825 1451 119 3. New measurements of 16O(n,alpha) cross sections at 14 MeV by 825 1451 120 Sanami and Baba [Sa97] were used to adjust the (n,alpha) cross 825 1451 121 sections. 825 1451 122 4. The neutron total cross section measurements of Finlay [Fi93] 825 1451 123 were incorporated into the evaluation above 7.3 MeV. Adjustments 825 1451 124 of up to 2% were made in the existing evaluation. 825 1451 125 5. The new evaluation contains no pseudo level or excitation 825 1451 126 energy bin data. Calculations were made with the GNASH code to 825 1451 127 provide continuum emission data in MF=6 format, as well as any 825 1451 128 unmeasured data. Calculated cross sections were renormalized 825 1451 129 whenever possible using experimental data. The GNASH calculations 825 1451 130 utilized transmission coefficients calculated with a spherical 825 1451 131 optical potential and level densities from the Gilbert and 825 1451 132 Cameron model, plus preequilibrium corrections using systematic 825 1451 133 values of parameters. 825 1451 134 6. Comparisons of the evaluation with a large body of 825 1451 135 experimental data have been made to validate the new data. 825 1451 136 825 1451 137 ------------------------------------------------------------------ 825 1451 138 825 1451 139 DETAILED DESCRIPTION REACTION BY REACTION 825 1451 140 825 1451 141 MF=2 RESONANCE PARAMETERS ------------------------------------- 825 1451 142 825 1451 143 The evaluation below 3.4 MeV is an R-function fit [Ca98] to 825 1451 144 experimental data using an optical model to provide a background 825 1451 145 R-function. The procedure is coded in the KAPL code "OPTIC", 825 1451 146 with an extension of the original code to convert the optical- 825 1451 147 model phase shifts to background R-functions. 825 1451 148 The analysis is carried to 3.4 MeV, where it is spliced to the 825 1451 149 LANL R-matrix analysis, with a transition region of about 60 keV 825 1451 150 centered at 3.4 MeV. 825 1451 151 From 3.4 to 6.25 MeV, a test evaluation was obtained from a new 825 1451 152 multi-channel R-matrix analysis of a large part of the available 825 1451 153 experimental data base using the EDA code. The analysis of the 825 1451 154 17O system includes data for n+16O neutron total cross sections 825 1451 155 and elastic scattering angular distributions, as well as data 825 1451 156 for the 16O(n,alpha) reaction in both the (n,alpha) and 825 1451 157 (alpha,n) directions. Also included are excitation functions 825 1451 158 for alpha+13C elastic scattering. The total cross sections in 825 1451 159 the final version of this analysis may change, especially in the 825 1451 160 region above 4 MeV. 825 1451 161 825 1451 162 Effective scattering radius = 5.56256E-13 cm. 825 1451 163 825 1451 164 MF=3 NEUTRON CROSS SECTIONS ----------------------------------- 825 1451 165 825 1451 166 THERMAL (2200 m/s) CROSS SECTIONS 825 1451 167 825 1451 168 TOTAL = 3.89440 B RADIATIVE CAPTURE= 0.1900 MB 825 1451 169 ELASTIC= 3.89421 B 825 1451 170 825 1451 171 MT=1 TOTAL CROSS SECTION 825 1451 172 0.0 to 3.40 MeV, calculated from R-function fit to total cross 825 1451 173 section and elastic angular distributions - see above. 825 1451 174 3.4 to 6.25 MeV, calculated from R-Matrix parameters by 825 1451 175 simultaneously fitting most of the available 16O(n,n)16O and 825 1451 176 16O(n,alpha0)13C data, as well as 13C(alpha,alpha)13C data at 825 1451 177 energies below En = 6.2 MeV. The experimental total cross 825 1451 178 section data fitted in the analysis were the [Jo74] results below 825 1451 179 6.26 MeV, and the [La80] measurements at higher energies, with 825 1451 180 inserts of the high-resolution data of [Jo79] over the resonances 825 1451 181 and in the window at En = 2.3-2.4 MeV. 825 1451 182 6.25 to 30 MeV, based on an adjustment of the covariance 825 1451 183 analysis used for the ENDF/B-VI (Rel. 0) evaluation to 825 1451 184 accommodate the new measurements of Finlay et al. [Fi93]. The 825 1451 185 previous ENDF/B-VI (Rel. 0) evaluations is based on analysis 825 1451 186 with the GLUCS Bayes code [He80] of the remaining major total 825 1451 187 cross section measurements [Fo71], [Pe72], [Sc72], [La80], 825 1451 188 [Ci68], [Ci80], with structure inserted from the high-resolution 825 1451 189 [Ci80] measurement. 825 1451 190 825 1451 191 MT=2 ELASTIC SCATTERING CROSS SECTION 825 1451 192 0.0 to 3.40 MeV, calculated from R-function fit to total cross 825 1451 193 section and elastic angular distributions - see above. 825 1451 194 3.4 to 6.25 MeV, R-matrix analysis that includes all available 825 1451 195 experimental data, as described above. Elastic angular 825 1451 196 distribution data used in the analysis includes [La60], [Ok55], 825 1451 197 [Fo58], [Ma62], [Fo70], [Hu62], [Ph61], [Jo67], [Ki72], [Ch61], 825 1451 198 [Dr76], [Fo64]. 825 1451 199 6.25 to 20 MeV, obtained by subtracting the nonelastic cross 825 1451 200 section (MT=3) from the total cross section (MT=1), although 825 1451 201 small adjustments were made to several of the less well 825 1451 202 determined reaction cross sections in order to enhance agreement 825 1451 203 with the elastic measurements of Borker [Bo89], Glendinning 825 1451 204 [Gl82], and Petler [Pe85]. The magnitude of these adjustments 825 1451 205 was generally small and was greatest near structure and near 825 1451 206 18 MeV. 825 1451 207 825 1451 208 MT=4 INELASTIC CROSS SECTION 825 1451 209 Threshold to 30 MeV, sum of MT=51-57, 91. 825 1451 210 825 1451 211 MT=51-57 INELASTIC CROSS SECTION TO DISCRETE STATES 825 1451 212 Threshold to 30 MeV, the (n,n') cross sections corresponding 825 1451 213 to gamma-emitting excited levels of 16O are included in MT=51-57 825 1451 214 as follows: 825 1451 215 MT=51 Ex= 6.0494 MeV 825 1451 216 MT=52 Ex= 6.129893 MeV 825 1451 217 MT=53 Ex= 6.9171 MeV 825 1451 218 MT=54 Ex= 7.11685 MeV 825 1451 219 MT=55 Ex= 8.8719 MeV 825 1451 220 MT=56 Ex=10.957 MeV 825 1451 221 MT=57 Ex=11.080 MeV 825 1451 222 825 1451 223 Note that the 16O levels at 9.585, 9.8445, and 10.356 are 825 1451 224 omitted because they decay primarily by alpha particle emission 825 1451 225 and those data are included in MT=22. 825 1451 226 825 1451 227 MT=16 (N,2N) CROSS SECTION 825 1451 228 Threshold to 30 MeV, based on GNASH calculation, renormalized 825 1451 229 down by approximately 30% to improve agreement with measurement 825 1451 230 of Brill et al. [Br61]. 825 1451 231 825 1451 232 MT=22 (N,NALPHA) CROSS SECTION 825 1451 233 Threshold to 30 MeV, based on GNASH calculation, with 825 1451 234 adjustments made to improve agreement with experimental data, 825 1451 235 especially data of Bormann et al. [Bo63]. 825 1451 236 825 1451 237 MT=23 (N,N3ALPHA) CROSS SECTION 825 1451 238 Threshold to 30 MeV, based on GNASH calculations, adjusted 825 1451 239 from 28 to 30 MeV to agree with LA150 data. 825 1451 240 825 1451 241 MT=28 (N,NP) CROSS SECTION 825 1451 242 Threshold to 30 MeV, based on GNASH calculations, adjusted 825 1451 243 such that the production cross sections for the 5.2701 and 5.2988 825 1451 244 MeV gamma rays are consistent with Nelson et al.[Ne99] data, and 825 1451 245 normalization of proton spectra consistent with 27-MeV data of 825 1451 246 Subramanian et al. [Su94]. 825 1451 247 825 1451 248 MT=32 (N,ND) CROSS SECTION 825 1451 249 Threshold to 30 MeV, based on GNASH calculations, adjusted 825 1451 250 such that difference between total and nonelastic cross sections 825 1451 251 agrees with elastic cross section measurements. 825 1451 252 825 1451 253 MT=41 (N,2NP) CROSS SECTION 825 1451 254 Threshold to 30 MeV, based on GNASH calculations, adjusted 825 1451 255 such that difference between total and nonelastic cross sections 825 1451 256 agrees with elastic cross section measurements. 825 1451 257 825 1451 258 MT=44 (N,N2P) CROSS SECTION 825 1451 259 Threshold to 30 MeV, based on GNASH calculations, adjusted 825 1451 260 such that difference between total and nonelastic cross sections 825 1451 261 agrees with elastic cross section measurements. 825 1451 262 825 1451 263 MT=45 (N,NPALPHA) CROSS SECTION 825 1451 264 Threshold to 30 MeV, based on GNASH calculations, adjusted 825 1451 265 such that difference between total and nonelastic cross sections 825 1451 266 agrees with elastic cross section measurements. 825 1451 267 825 1451 268 MT=91 (N,N'CONTINUUM) CROSS SECTION 825 1451 269 Threshold to 30 MeV, based on GNASH calculations, adjusted 825 1451 270 such that difference between total and nonelastic cross sections 825 1451 271 agrees with elastic cross section measurements. 825 1451 272 825 1451 273 MT=102 (N,GAMMA) CROSS SECTION 825 1451 274 0 to 1 MeV,cross section based on experimental data obtained 825 1451 275 from E. Jurney [Ju64]; higher energy data is crude estimate. 825 1451 276 825 1451 277 MT=103 (N,P) CROSS SECTION 825 1451 278 Sum of MT=600-603. 825 1451 279 825 1451 280 MT=104 (N,D) CROSS SECTION 825 1451 281 Sum of MT=650-669. 825 1451 282 825 1451 283 MT=105 (N,T) CROSS SECTION 825 1451 284 Sum of MT=700-709,749. 825 1451 285 825 1451 286 MT=107 (N,ALPHA) CROSS SECTION 825 1451 287 Sum of MT=800-803. 825 1451 288 825 1451 289 MT=108 (N,2ALPHA) CROSS SECTION 825 1451 290 Threshold to 30 MeV, based on GNASH calculations, adjusted 825 1451 291 such that difference between total and nonelastic cross sections 825 1451 292 agrees with elastic cross section measurements. 825 1451 293 825 1451 294 MT=112 (N,PALPHA) CROSS SECTION 825 1451 295 Threshold to 30 MeV, based on GNASH calculations, adjusted 825 1451 296 such that difference between total and nonelastic cross sections 825 1451 297 agrees with elastic cross section measurements. 825 1451 298 825 1451 299 MT=600 (N,P) INTEGRATED CROSS SECTION TO 16N GROUND STATE 825 1451 300 Threshold to 30 MeV, based on GNASH calculations with some 825 1451 301 renormalization (lowered approximately 30%) from comparison of 825 1451 302 excited state predictions with Nelson et al. [Ne99] 825 1451 303 measurements. 825 1451 304 825 1451 305 MT=601-603 (N,P) CROSS SECTION TO EXCITED LEVELS OF 16N 825 1451 306 Threshold to 30 MeV, the cross sections for the 0.0.297- and 825 1451 307 0.3975-MeV levels are inferred from the (n,p gamma) data of 825 1451 308 Nelson et al. [Ne99], using the level structure diagram of 16N 825 1451 309 by Ajzenberg-Selove [Aj86]. The cross section for the 0.1201- 825 1451 310 MeV level is based on GNASH calculations with some 825 1451 311 renormalization (lowered ~30%) from comparison of excited state 825 1451 312 predictions with Nelson et al. [Ne99] measurements. 825 1451 313 825 1451 314 MT=650 (N,D) INTEGRATED CROSS SECTION TO 15N GROUND STATE 825 1451 315 Threshold to 30 MeV, based on GNASH calculations with some 825 1451 316 renormalization from comparison of excited state predictions 825 1451 317 with Nelson et al. [Ne99] measurements. 825 1451 318 825 1451 319 MT=651-669 (N,D) CROSS SECTION TO EXCITED LEVELS OF 15N 825 1451 320 Threshold to 30 MeV, the cross sections for the 5.2701- and 825 1451 321 5.2988-MeV levels are adjusted based on the (n,xgamma) data of 825 1451 322 Nelson et al. [Ne99], using the level structure diagram for 15N 825 1451 323 by Ajzenberg-Selove [Aj91]. Cross sections for remaining levels 825 1451 324 are based on GNASH calculations with some renormalization from 825 1451 325 comparison of excited state predictions with Nelson et al. 825 1451 326 [Ne99] measurements and 27-Mev data of Subramanian et al. [Su94]. 825 1451 327 825 1451 328 MT=700 (N,T) INTEGRATED CROSS SECTION TO 14N GROUND STATE 825 1451 329 Threshold to 30 MeV, based on GNASH calculations with some 825 1451 330 renormalization from comparison of excited state predictions 825 1451 331 with Nelson et al. [Ne99] measurements. 825 1451 332 825 1451 333 MT=701-709 (N,T) CROSS SECTION TO EXCITED LEVELS OF 14N 825 1451 334 Threshold to 30 MeV, the cross section for the 2.3128-MeV 825 1451 335 levels is inferred from the (n,t gamma) data of Nelson et al. 825 1451 336 [Ne99], using the level structure diagram for 16N by Ajzenberg- 825 1451 337 Selove [Aj91]. Cross sections for the remaining levels are 825 1451 338 based on GNASH calculations with some renormalization from 825 1451 339 comparison of excited state predictions with Nelson et al. 825 1451 340 [Ne99] measurements. 825 1451 341 825 1451 342 MT=749 (N,T) CROSS SECTION TO 14N CONTINUUM 825 1451 343 Threshold to 30 MeV, based on GNASH calculations with some 825 1451 344 renormalization from comparison of excited state predictions 825 1451 345 with Nelson et al. [Ne99] measurements and to enhance agreement 825 1451 346 of elastic cross section with measured data. 825 1451 347 825 1451 348 MT=800 (N,ALPHA0) CROSS SECTION TO 13C GROUND STATE 825 1451 349 0.0 to 6.2 MeV, based on R-matrix analysis described above 825 1451 350 under MT=1. Data of Ba72 were used in the original (alpha,n) 825 1451 351 direction, with no changes in energy scale or normalization. 825 1451 352 Also included were the low-energy (alpha,n) data of [Ke91] and 825 1451 353 [Dr93]. 825 1451 354 6.2 to 20 MeV, based on data of [Da63],[Da68],[Si68],[Ba73], 825 1451 355 and composite of [Mc66b],[Ma68],[Le68] at 14 MeV. Note that the 825 1451 356 [Da63] data were renormalized by factor of 1.5 to bring them 825 1451 357 into rough agreement with the R-matrix analysis of the [Ba73] 825 1451 358 (n,a0) data, together with the total and elastic data in the 825 1451 359 analysis. Because the [Da68] experimental data were normalized 825 1451 360 to [Da63], the former were also renormalized by the factor of 825 1451 361 1.5. 825 1451 362 825 1451 363 MT=801-803 (N,ALPHA) CROSS SECTION TO EXCITED LEVELS OF 13C 825 1451 364 Threshold to 30 MeV, the cross sections of the 3.0894-, 825 1451 365 3.6845-, and 3.8538-MeV levels are inferred from the (n,alpha 825 1451 366 gamma) data of Nelson et al. [Ne99], using the level structure 825 1451 367 diagram of 13C by Ajzenberg-Selove [Aj91]. 825 1451 368 825 1451 369 MF=4 ANGULAR DISTRIBUTIONS ------------------------------------ 825 1451 370 825 1451 371 MT=2 ELASTIC NEUTRON ANGULAR DISTRIBUTIONS 825 1451 372 0.0 to 3.4 MeV, calculated from R-function fit (see MF=3,MT=1). 825 1451 373 3.4 to 6.2 MeV, calculated from R-matrix fit (see MF=3,MT=1). 825 1451 374 Measured angular distributions input to the fit were those of 825 1451 375 [Ch61],[Fo58],[Fo70],[Hi58],[Hu62], [Jo67],[Ki72],[La60],[Li66], 825 1451 376 [Ma62],[Ph61],[Jo79]. Fits were attempted using new data of 825 1451 377 [Sc77], but those measurements were found to have significant 825 1451 378 uncertainties, and some discrepancies with other data were noted. 825 1451 379 6.2 to 20 MeV, smooth curve through coefficients derived from 825 1451 380 fits to elastic data of [Ph61],[Ne72],[Ch61],[Ba63],[Be67], 825 1451 381 [Mc66a],[Ki72],[Bu73],[Ne72],[Gl82],[Ba85],[Bo89],[Pe85]. 825 1451 382 825 1451 383 MT=51-57 DISCRETE (N,N') ANGULAR DISTRIBUTIONS 825 1451 384 Threshold to 10 MeV, assumed isotropic in center of mass. 825 1451 385 Above 10 MeV, based on fits of the 14-MeV data of [Ki72],[Ne72], 825 1451 386 [Ba63],[Mc66a],[Ba85],[Me69], and especially [Bo89]. 825 1451 387 825 1451 388 MT=600-603 DISCRETE (N,P) ANGULAR DISTRIBUTIONS 825 1451 389 Threshold to 30 MeV, assumed isotropic in center of mass. 825 1451 390 825 1451 391 MT=650-669 DISCRETE (N,D) ANGULAR DISTRIBUTIONS 825 1451 392 Threshold to 30 MeV, assumed isotropic in center of mass. 825 1451 393 825 1451 394 MT=700-709 DISCRETE (N,T) ANGULAR DISTRIBUTIONS 825 1451 395 Threshold to 30 MeV, assumed isotropic in center of mass. 825 1451 396 825 1451 397 MT=800 DISCRETE(N,ALPHA0) ANGULAR DISTRIBUTIONS 825 1451 398 0.0 to 6.2 MeV, calculated from R-Matrix fit (see MF=3,MT=1). 825 1451 399 Measured angular distributions input to the fit were 825 1451 400 reconstructed from the Legendre coefficients of [Wa57], and 825 1451 401 converted to (n,alpha) angular distributions using detailed 825 1451 402 balance. 825 1451 403 825 1451 404 MT=801-803 DISCRETE (N,T) ANGULAR DISTRIBUTIONS 825 1451 405 Threshold to 6 MeV, 825 1451 406 6 to 30 MeV, assumed isotropic in center of mass. 825 1451 407 825 1451 408 MF=6 PRODUCT ENERGY-ANGLE DISTRIBUTIONS ----------------------- 825 1451 409 825 1451 410 MT=16 (N,2N) CONTINUUM ENERGY-ANGLE EMISSION DATA 825 1451 411 Threshold to 30 MeV, energy-angle correlated energy spectra 825 1451 412 are given for neutrons, and isotropic energy spectra are given 825 1451 413 for recoiling 15O nuclei. The neutron data were obtained from 825 1451 414 the GNASH calculations; the recoil 15O distributions were 825 1451 415 calculated with the RECOIL code [Ma83]. The discrete gamma rays 825 1451 416 from (n,2ngamma) reactions are given in MF=13 and 14. 825 1451 417 825 1451 418 MT=22 (N,NALPHA) CONTINUUM ENERGY-ANGLE EMISSION DATA 825 1451 419 Threshold to 30 MeV, energy-angle correlated energy spectra 825 1451 420 are given for neutrons and alpha particles, and isotropic energy 825 1451 421 spectra are given for recoiling 12C nuclei. The neutron and 825 1451 422 alpha data were obtained from the GNASH calculations; the recoil 825 1451 423 12C distributions were calculated with the RECOIL code [Ma83]. 825 1451 424 The discrete gamma rays from (n,nalpha gamma) reactions are 825 1451 425 given in MF=13 and 14. 825 1451 426 825 1451 427 MT=28 (N,NP) CONTINUUM ENERGY-ANGLE EMISSION DATA 825 1451 428 Threshold to 30 MeV, energy-angle correlated energy spectra 825 1451 429 are given for neutrons and protons; isotropic energy spectra are 825 1451 430 given for recoiling 15N nuclei; and isotropic energy spectra are 825 1451 431 given for emitted continuum gamma rays. The neutron, proton, 825 1451 432 and gamma-ray data were obtained from the GNASH calculations; 825 1451 433 the recoil 15N distributions were calculated with the RECOIL 825 1451 434 code [Ma83]. 825 1451 435 825 1451 436 MT=32 (N,ND) CONTINUUM ENERGY-ANGLE EMISSION DATA 825 1451 437 Threshold to 30 MeV, energy-angle correlated energy spectra 825 1451 438 are given for neutrons and deuterons; isotropic energy spectra 825 1451 439 are given for recoiling 14N nuclei; and isotropic energy spectra 825 1451 440 are given for emitted continuum gamma rays. The neutron, 825 1451 441 deuteron, and gamma-ray data were obtained from the GNASH 825 1451 442 calculations; the recoil 14N distributions were calculated with 825 1451 443 the RECOIL code [Ma83]. 825 1451 444 825 1451 445 MT=41 (N,2NP) CONTINUUM ENERGY-ANGLE EMISSION DATA 825 1451 446 Threshold to 30 MeV, energy-angle correlated energy spectra 825 1451 447 are given for neutrons and protons; isotropic energy spectra are 825 1451 448 given for recoiling 14N nuclei; and isotropic energy spectra are 825 1451 449 given for emitted continuum gamma rays. The neutron, proton, 825 1451 450 and gamma-ray data were obtained from the GNASH calculations; 825 1451 451 the recoil 14N distributions were calculated with the RECOIL 825 1451 452 code [Ma83]. 825 1451 453 825 1451 454 MT=44 (N,N2P) CONTINUUM ENERGY-ANGLE EMISSION DATA 825 1451 455 Threshold to 30 MeV, energy-angle correlated energy spectra 825 1451 456 are given for neutrons and protons; isotropic energy spectra are 825 1451 457 given for recoiling 14C nuclei; and isotropic energy spectra are 825 1451 458 given for emitted continuum gamma rays. The neutron, proton, 825 1451 459 and gamma-ray data were obtained from the GNASH calculations; 825 1451 460 the recoil 14C distributions were calculated with the RECOIL 825 1451 461 code [Ma83]. 825 1451 462 825 1451 463 MT=45 (N,NPALPHA) CONTINUUM ENERGY-ANGLE EMISSION DATA 825 1451 464 Threshold to 30 MeV, energy-angle correlated energy spectra 825 1451 465 are given for neutrons, protons, and alphas; isotropic energy 825 1451 466 spectra are given for recoiling 11B nuclei; and isotropic energy 825 1451 467 spectra are given for emitted continuum gamma rays. The 825 1451 468 neutron, proton, alpha, and gamma-ray data were obtained from 825 1451 469 the GNASH calculations; the recoil 11B distributions were 825 1451 470 calculated with the RECOIL code [Ma83]. 825 1451 471 825 1451 472 MT=91 (N,N'CONTINUUM) CONTINUUM ENERGY-ANGLE EMISSION DATA 825 1451 473 Threshold to 30 MeV, energy-angle correlated energy spectra 825 1451 474 are given for neutrons; isotropic energy spectra are given for 825 1451 475 recoiling 16O nuclei; and isotropic energy spectra are given for 825 1451 476 emitted continuum gamma rays. The neutron and gamma-ray data 825 1451 477 were obtained from the GNASH calculations; the recoil 16O 825 1451 478 distributions were calculated with the RECOIL code [Ma83]. 825 1451 479 825 1451 480 MT=108 (N,2ALPHA) CONTINUUM ENERGY-ANGLE EMISSION DATA 825 1451 481 Threshold to 30 MeV, energy-angle correlated energy spectra 825 1451 482 are given for alphas; isotropic energy spectra are given for 825 1451 483 recoiling 9Be nuclei; and isotropic energy spectra are given for 825 1451 484 emitted continuum gamma rays. The alpha, and gamma-ray data 825 1451 485 were obtained from the GNASH calculations; the recoil 9Be 825 1451 486 distributions were calculated with the RECOIL code [Ma83]. 825 1451 487 825 1451 488 MT=112 (N,PALPHA) CONTINUUM ENERGY-ANGLE EMISSION DATA 825 1451 489 Threshold to 30 MeV, energy-angle correlated energy spectra 825 1451 490 are given for protons, and alphas; isotropic energy spectra are 825 1451 491 given for recoiling 12B nuclei; and isotropic energy spectra are 825 1451 492 given for emitted continuum gamma rays. The proton, alpha, and 825 1451 493 gamma-ray data were obtained from the GNASH calculations; the 825 1451 494 recoil 12B distributions were calculated with the RECOIL code 825 1451 495 [Ma83]. 825 1451 496 825 1451 497 MT=749 (N,ALPHA) CONTINUUM ENERGY-ANGLE EMISSION DATA 825 1451 498 Threshold to 30 MeV, energy-angle correlated energy spectra 825 1451 499 are given for alpha particles; isotropic energy spectra are 825 1451 500 given for recoiling 13C nuclei; and isotropic energy spectra are 825 1451 501 given for emitted continuum gamma rays. The alpha and gamma-ray 825 1451 502 data were obtained from the GNASH calculations; the recoil 13C 825 1451 503 distributions were calculated with the RECOIL code [Ma83]. 825 1451 504 825 1451 505 MF=12 PHOTON PRODUCTION MULTIPLICITIES ------------------------ 825 1451 506 825 1451 507 MT=102 (N,GAMMA) PHOTON PRODUCTION MULTIPLICITIES 825 1451 508 Photon multiplicities for radiative capture are based on 825 1451 509 experimental data obtained from Jurney [Ju64]. 825 1451 510 825 1451 511 MF=13 PHOTON PRODUCTION CROSS SECTIONS ------------------------ 825 1451 512 825 1451 513 MT=4 (N,N'GAMMA) PHOTON PRODUCTION CROSS SECTIONS 825 1451 514 Threshold to 30 MeV: Based almost entirely on new angular 825 1451 515 distribution measurements by Nelson et al. [Ne99], which 825 1451 516 utilized a white neutron source and covered the energy range 825 1451 517 from threshold to 200 MeV. The measurements were made at 7 825 1451 518 angles using high-resolution Ge detectors and resulted in data 825 1451 519 for some 23 gamma rays from 7 different reactions. The angular 825 1451 520 distributions were fit with Legendre expansions to obtain angle- 825 1451 521 integrated cross sections. The fitted cross sections were 825 1451 522 smoothed somewhat for this evaluation, although much of the 825 1451 523 measured structure was preserved, particularly for the intense 825 1451 524 6.129-MeV gamma. The evaluated data for the following gamma 825 1451 525 rays are based directly on the measurements: 825 1451 526 825 1451 527 EG= 2.742 MeV (decay of 8.8719-MeV level of 16O) 825 1451 528 EG= 3.839 MeV (decay of 10.957-MeV level of 16O) 825 1451 529 EG= 4.950 MeV (decay of 11.080-MeV level of 16O) 825 1451 530 EG= 6.130 MeV (decay of 6.130-MeV level of 16O) 825 1451 531 EG= 6.917 MeV (decay of 6.917-MeV level of 16O) 825 1451 532 EG= 7.117 MeV (decay of 7.117-MeV level of 16O) 825 1451 533 825 1451 534 The evaluated cross sections for the remaining (n,n') gamma 825 1451 535 rays are inferred from these data using the energy level scheme 825 1451 536 of Ajzenberg-Selove [Aj86]. Data were also obtained for gamma 825 1451 537 rays of energy 1.755 and 1.955 from decay of the 8.8719-MeV 825 1451 538 level but the 2.742-MeV gamma was used to determine the level 825 1451 539 excitation cross section because it is the most intense. 825 1451 540 Similarly, data were obtained on a 4.179-MeV gamma from decay of 825 1451 541 the 11.080-MeV level, but the 4.950-MeV gamma is more intense 825 1451 542 and was used to determine the level excitation cross section. 825 1451 543 The evaluated data were compared to older gamma-ray 825 1451 544 measurements by [Be70], [Ne90], [No78], [Ha59], [Di70], [Or70], 825 1451 545 [Dr70], [Cl69], [Lu70], [Bu71], [Ny69]. Considering that very 825 1451 546 few (e.g., [Be70], [Dr70]) of these measurements are of full 825 1451 547 angular distributions, the agreement is reasonable. 825 1451 548 825 1451 549 MT=16 (N,2NGAMMA) PHOTON PRODUCTION CROSS SECTIONS 825 1451 550 Threshold to 30 MeV: The cross section for the 5.2409-MeV 825 1451 551 gamma ray was obtained directly from the Nelson et al. [Ne99] 825 1451 552 data. The remaining discrete gammas are based on GNASH 825 1451 553 calculations, with some renomalization based on the experimental 825 1451 554 data. 825 1451 555 825 1451 556 MT=22 (N,NALPHA GAMMA) PHOTON PRODUCTION CROSS SECTIONS 825 1451 557 Threshold to 30 MeV: Only the 4.438-MeV discrete gamma ray 825 1451 558 is given and it is based on the Nelson et al. [Ne99] data. 825 1451 559 825 1451 560 MT=103 (N,PGAMMA) PHOTON PRODUCTION CROSS SECTIONS 825 1451 561 Threshold to 30 MeV: The cross sections for the 0.2774- and 825 1451 562 0.297-MeV gamma rays are based on the Nelson et al. [Ne99] data. 825 1451 563 The 0.3975-MeV gamma is inferred from the 0.2774-MeV gamma data 825 1451 564 through the Ajzenberg-Selove level scheme [Aj86] for 16N. The 825 1451 565 0.1201-MeV gamma cross section is based partially on GNASH 825 1451 566 calculations and partially inferred from the [Ne99] data using 825 1451 567 the 16N level scheme. 825 1451 568 825 1451 569 MT=104 (N,DGAMMA) PHOTON PRODUCTION CROSS SECTIONS 825 1451 570 Threshold to 30 MeV: The cross sections for the 5.2701- and 825 1451 571 5.2988-MeV gamma rays are based on the Nelson et al. [Ne99] 825 1451 572 data. The cross sections for the remaining 60 (n,dg) gamma rays 825 1451 573 are based on GNASH calculations and the Ajzenberg-Selove level 825 1451 574 scheme [Aj91] for 15N, after renomalization to agree with the 825 1451 575 measured 5.2701- and 5.2988-MeV gamma-ray data. 825 1451 576 825 1451 577 MT=105 (N,TGAMMA) PHOTON PRODUCTION CROSS SECTIONS 825 1451 578 Threshold to 30 MeV: The cross section for the 2.313-MeV 825 1451 579 gamma ray is based on the Nelson et al. [Ne99] measurement. The 825 1451 580 cross sections for the remaining 20 (n,tg) gamma rays are based 825 1451 581 on GNASH calculations and the Ajzenberg-Selove level scheme 825 1451 582 [Aj91] for 14N, after renomalization to agree with the measured 825 1451 583 2.313-MeV gamma-ray data. 825 1451 584 825 1451 585 MT=107 (N,ALPHA GAMMA) PHOTON PRODUCTION CROSS SECTIONS 825 1451 586 Threshold to 30 MeV: The cross sections for the 3.0894-, 825 1451 587 3.6845- and 3.8538-MeV gamma rays are based on the Nelson et 825 1451 588 al. [Ne99] data. The 0.1693-, 0.5951- and 0.7644-MeV gamma-ray 825 1451 589 cross sections are inferred from the above data through the 825 1451 590 Ajzenberg-Selove level scheme [Aj91]. Note that the 0.1693-MeV 825 1451 591 gamma from decay of the 3.8538-MeV level also was measured, but 825 1451 592 the 3.8538-MeV gamma is more intense and was used to determine 825 1451 593 the level excitation cross section. 825 1451 594 825 1451 595 MF=14 PHOTON ANGULAR DISTRIBUTIONS ---------------------------- 825 1451 596 825 1451 597 MT=4 (N,N'GAMMA) PHOTON ANGULAR DISTRIBUTIONS 825 1451 598 Anisotropic angular distributions in Legendre polynomial 825 1451 599 representation are given for the 1.755-, 2.742-, 6.130-, 6.917-, 825 1451 600 and 7.117-MeV gamma rays, obtained by fitting the measurements 825 1451 601 of Nelson et al. [Ne99]. Isotropic angular distributions are 825 1451 602 assumed for the remaining gamma rays. 825 1451 603 825 1451 604 MT=16 (N,2NGAMMA) PHOTON ANGULAR DISTRIBUTIONS 825 1451 605 An anisotropic angular distribution in Legendre polynomial 825 1451 606 representation is given for the 5.2409-MeV gamma ray, obtained 825 1451 607 by fitting the measurements of Nelson et al. [Ne99]. Isotropic 825 1451 608 angular distributions are assumed for the remaining gamma rays. 825 1451 609 825 1451 610 MT=22 (N,NALPHA GAMMA) PHOTON ANGULAR DISTRIBUTIONS 825 1451 611 An anisotropic angular distribution in Legendre polynomial 825 1451 612 representation is given for the 4.438-MeV gamma ray, obtained by 825 1451 613 fitting the measurements of Nelson et al. [Ne99]. 825 1451 614 825 1451 615 MT=102 (N,GAMMA) PHOTON ANGULAR DISTRIBUTIONS 825 1451 616 All gamma rays from radiative capture are assumed to be 825 1451 617 isotropic. 825 1451 618 825 1451 619 MT=103 (N,PGAMMA) PHOTON ANGULAR DISTRIBUTIONS 825 1451 620 Anisotropic angular distributions in Legendre polynomial 825 1451 621 representation are given for the 0.2774-, 0.297-, and 0.3975-MeV 825 1451 622 gamma rays, obtained by fitting the measurements of Nelson et 825 1451 623 al. [Ne99]. The angular distributions for all remaining gamma 825 1451 624 rays are assumed to be isotropic. 825 1451 625 825 1451 626 MT=104 (N,DGAMMA) PHOTON ANGULAR DISTRIBUTIONS 825 1451 627 An anisotropic angular distribution in Legendre polynomial 825 1451 628 representation is given for the 5.2701-MeV gamma ray, obtained 825 1451 629 by fitting the measurements of Nelson et al. [Ne99]. The 825 1451 630 angular distributions for all remaining gamma rays are assumed 825 1451 631 to be isotropic. 825 1451 632 825 1451 633 MT=105 (N,TGAMMA) PHOTON ANGULAR DISTRIBUTIONS 825 1451 634 All gamma rays from (n,tg) reactions are assumed to be 825 1451 635 isotropic. 825 1451 636 825 1451 637 MT=107 (N,ALPHA GAMMA) PHOTON ANGULAR DISTRIBUTIONS 825 1451 638 Anisotropic angular distributions in Legendre polynomial 825 1451 639 representation are given for the 0.1693-, 3.6845- and 3.8538- 825 1451 640 MeV gamma rays, obtained by fitting the measurements of Nelson 825 1451 641 et al. [Ne99]. Isotropic angular distributions are assumed for 825 1451 642 all the remaining gamma rays. 825 1451 643 825 1451 644 **************************************************************** 825 1451 645 825 1451 646 SUMMARY OF DATA VALIDATION OF THIS FILE AGAINST INTEGRAL 825 1451 647 BENCHMARKS 825 1451 648 825 1451 649 KAPL (Weinman, Caro, Lubitz) performed a number of data 825 1451 650 validation benchmark calculations to test the performance of this 825 1451 651 file (June-August 2001). This O16 evaluation gives consistently 825 1451 652 good results for the 21 CSWEG solution critical calculations, the 825 1451 653 liquid-oxygen broomstick neutron-transmission experiment, and the 825 1451 654 neutron age in water experiment (see below for more details). 825 1451 655 825 1451 656 A) 21 CSWEG solution critical calculations. Weinman calculated a 825 1451 657 set of 21 ORNL and Rocky Flats benchmark solution criticals used 825 1451 658 for CSEWG analyses. These calculations were run with ENDF/B-VI 825 1451 659 release 5 U235 (Leal,Larson,wright,Derrien) and hydrogen (332.0 825 1451 660 mbarns 2200m/s). Four different oxygen 16 cross section 825 1451 661 evaluations were considered. 825 1451 662 825 1451 663 1. KAPL-Caro 825 1451 664 2. This evaluation (which contains the KAPL data below 3.4 MeV) 825 1451 665 3. ENDF/B-VI MOD 2 825 1451 666 4. JENDL 3.2 825 1451 667 825 1451 668 All four O16 cross section evaluations gave good reactivity 825 1451 669 responses versus our fitting parameter above-thermal-leakage ATL. 825 1451 670 The ATL parameter is a sensitive trending variable to high energy 825 1451 671 scattering cross sections. All four O16 evaluations produced 825 1451 672 eigenvalues whose mean values were all close to unity and only 825 1451 673 the older ENDF/B-VI.2 cross section evaluation gave a slight 825 1451 674 reactivity trend (about .0020 Delta Keff over the range). The 825 1451 675 average eigenvalues and slopes are listed below. 825 1451 676 825 1451 677 Library Av. Keff Slope 825 1451 678 825 1451 679 KAPL-Caro 0.9993 +.0001 825 1451 680 This file 0.9996 +.0004 825 1451 681 ENDF/B-VI.2 1.0003 +.0032 825 1451 682 JENDL 3.2 1.0004 -.0002 825 1451 683 825 1451 684 Thus the reactivity trend, labeled "slope" in the table above, is 825 1451 685 much smaller in the new file compared to the previous ENDF/B-VI.2 825 1451 686 evaluation. 825 1451 687 825 1451 688 B) The liquid-oxygen broomstick experiment. The oxygen window at 825 1451 689 2.3 MeV is the most important feature at which energy the 825 1451 690 greatest transmission takes place. The new evaluation produces 825 1451 691 close to exact agreement with the experiment in the energy range 825 1451 692 of the oxygen window. The previous ENDF/B-VI value is slightly 825 1451 693 below the experimental value. At energies higher than 5.5 MeV, 825 1451 694 the new evaluation produces slightly better results than does the 825 1451 695 previous ENDF/B-VI results. 825 1451 696 825 1451 697 C) Neutron age in water. KAPL obtained 26.4 to be compared 825 1451 698 against an experimental value of 26.6 +/- 0.6. The previous 825 1451 699 ENDF/B-VI file gave a result of 26.3. 825 1451 700 825 1451 701 Additionally, A.C. (Skip) Kahler at Bettis lab undertook 825 1451 702 benchmark testing of this file (memo, May 16, 2001) against 825 1451 703 thermal benchmarks documented in the Int. Handbook of Evaluated 825 1451 704 Criticality Safety Benchmark Experiments, as well as the L5 and 825 1451 705 L6 ORNL benchmarks. From a thermal reactor benchmark perspective, 825 1451 706 there is little to distinguish the performance of the present 825 1451 707 file compared to the previous ENDF file and JENDL-3.2. 825 1451 708 825 1451 709 ***************************************************************** 825 1451 710 825 1451 711 REFERENCES 825 1451 712 825 1451 713 [Aj86] F. Ajzenberg-Selove, Nucl.Phys. A460, 1 (1986) 825 1451 714 [Aj91] F. Ajzenberg-Selove, Nucl.Phys. A523, 1 (1991) 825 1451 715 [Ba63] R.W. Bauer et al., Nucl.Phys. 47, 241 (1963) 825 1451 716 [Ba73] J.K. Bair and F.X. Haas, Phys.Rev.C 7, 1356 (1973) 825 1451 717 (n,a0) cross sect. obtained by detailed balance from this ref. 825 1451 718 [Ba85] M. Baba et al., Nuclear Data for Basic and Applied Sci., 825 1451 719 Proc. Conf., Santa Fe, NM, May 1985, Vol.1 (Gordon and Breach, 825 1451 720 1986) p.223 825 1451 721 [Be67] P.L. Beach et al., Phys.Rev. 156, 1201 (1967) 825 1451 722 [Be70] P. Bertin, report CEA-R-4047 (1970) 825 1451 723 [Bo63] M. Bormann et al., Zeits.Physik 174, 1 (1963) 825 1451 724 [Bo89] G. Borker, W. Mannhart, et al., report PTB-N-1 (1989) and 825 1451 725 private communication 825 1451 726 [Br61] Brill, Sov.Phys.D. 6, 24 (1961) 825 1451 727 [Bu71] P.S. Buchanan, et al., report ORO-2791-32 (1971) 825 1451 728 [Bu73] W.P. Bucher et al., report BRL-R-1652 (1973) 825 1451 729 [Ca98] E. Caro, "O16 Neutron Cross Section Evaluation", 825 1451 730 Proceedings of the International Conference on the Physics of 825 1451 731 Nuclear Science and Technology Long Island, N.Y., Oct.5-8, 1998. 825 1451 732 [Ch61] L.F. Chase et al., report AFSWC-TR-61-15 (1961) 825 1451 733 [Ch93] M.B. Chadwick and P G. Young, Phys.Rev. C 47, 2255 (1993) 825 1451 734 [Ch96a] M.B. Chadwick and P.G. Young, Nucl.Sci.Eng. 123, 1 (1996) 825 1451 735 [Ch96b] M.B. Chadwick, P.G. Young, R.E. MacFarlane, and A.J. 825 1451 736 Koning, "High-Energy Nuclear Data Libraries for Accelerator- 825 1451 737 Driven Technologies: Calculational Method for Heavy Recoils," 825 1451 738 Proc. of 2nd Int. Conf. on Accelerator Driven Transmutation 825 1451 739 Technology and Applications, Kalmar, Sweden, 3-7 June 1996. 825 1451 740 [Ch99] M.B. Chadwick, P.G. Young, G.M. Hale, et al., Los Alamos 825 1451 741 National Laboratory report, LA-UR-99-1222 (1999) 825 1451 742 [Ci68] S. Cierjacks et al., report KFK-1000 (1968) 825 1451 743 [Ci80] S. Cierjacks et al., Nucl.Inst.Meth. 169, 185 (1980) 825 1451 744 [Cl69] G. Clayeux and G. Grenier, report CEA-R-3807 (1969) 825 1451 745 [Co67] J.L. Cook, H. Ferguson, and A.R. De L Musgrove, Aust.J. 825 1451 746 Phys. 20, 477 (1967) 825 1451 747 [Da63] E.A. Davis et al., Nucl.Phys. 48, 169 (1963) 825 1451 748 [Da68] D. Dandy et al., report AWRE O60/68 (1968) 825 1451 749 [Di70] J.K. Dickens and F.G. Perey, Nucl.Sci.Eng. 40, 283 (1970) 825 1451 750 [Dr70] D.M. Drake et al., Nucl.Sci.Eng. 40, 294 (1970) 825 1451 751 [Dr76] L. Drigo et al., Nuovo cim. A 31 (1), 1 (1976) 825 1451 752 [Dr93] H.W.Drotleff et al., Ap.J. 414, 735 (1993) 825 1451 753 [Fi93] R. Finlay et al., Phys.Rev. C 47, 237 (1993) 825 1451 754 [Fo58] J.L. Fowler and H.O. Cohn, Phys.Rev. 109, 89 (1958) 825 1451 755 [Fo64] J.L. Fowler and C.H. Johnson, report ORNL-3582 (1964) p.90 825 1451 756 [Fo70] J.L. Fowler and C.H. Johnson, Phys.Rev.C 2,124 (1970) 825 1451 757 [Fo71] D.G. Foster and D.W. Glasgow, Phys.Rev.C 3, 576 (1971) 825 1451 758 [Gl82] S.L. Glendinning et al., Nuc.Sci.Eng. 82, 393 (1982) 825 1451 759 [Ha59] H.E. Hall et al., Nucl.Phys. 14, 295 (1959) 825 1451 760 [Ha92] G.M. Hale, P.G. Young, M. Chadwick, and Z.-P. Chen, 825 1451 761 Nuclear Data for Science and Technology, Proc. Conf., Juelich, 825 1451 762 Germany, May 1991 [LA-UR-91-1516], (Ed. S. M. Qaim, Springer- 825 1451 763 Verlag, Germany, 1992), p.921 825 1451 764 [He80] D.M. Hetrick and C.Y. Fu, report ORNL/TM-7341 (1980) 825 1451 765 [Hi58] R.W. Hill, Phys.Rev. 109, 2105 (1958) 825 1451 766 [Hu62] W. Hunzinger and P. Huber, Helv.Phys.Acta 35, 351 (1962) 825 1451 767 [Ig75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov.J. 825 1451 768 Nucl.Phys. 21, 255 (1975); transl. of Yad.Fiz. 21, 485 (1975) 825 1451 769 [Jo67] C.H. Johnson and J.L. Fowler, Phys.Rev. 162, 890 (1967) 825 1451 770 [Jo73] C.H. Johnson, Phys.Rev.C 7, 561 (1973) 825 1451 771 [Jo74] C.H. Johnson et al., report ORNL-4937 (1974) 825 1451 772 [Jo79] C.H. Johnson, et al., Nuclear Cross Sections for 825 1451 773 Technology, Proc. Conf., Knoxville, TN, Oct. 1979 (National 825 1451 774 Bureau of Standards, 1980) p.807 825 1451 775 [Ju64] E.T. Jurney and H.T. Motz, Bull.Am.Phys.Soc. 9, 176 (1964) 825 1451 776 [Ka77] C. Kalbach, Z.Phys.A 283, 401 (1977) 825 1451 777 [Ka85] C. Kalbach, Los Alamos National Laboratory report 825 1451 778 LA-10248-MS (1985) 825 1451 779 [Ka88] C. Kalbach, Phys.Rev.C 37, 2350 (1988); see also 825 1451 780 C. Kalbach and F. M. Mann, Phys.Rev.C 23, 112 (1981) 825 1451 781 [Ke93] S.Kellogg, reported by C.R.Brune et al., Phys. Rev. C 48, 825 1451 782 3119 (1993). Data renormalized substantially. 825 1451 783 [Ki72] W.E. Kinney and F.G. Perey, report ORNL-4780 (1972) 825 1451 784 [Ko90] J. Kopecky and M. Uhl, Phys.Rev.C 41, 1941 (1990) 825 1451 785 [La60] R.O. Lane et.al., Argonne report ANL-6172 (1960) 825 1451 786 [La80] D. Larson et al., Symp. on Neutron Cross Sections from 10 825 1451 787 to 50 MeV, BNL, May 1980, report BNL-NCS-51243, Vol. 1 (1980) 825 1451 788 p.277 and private communication (1989) 825 1451 789 [Le68] B. Leroux et al., Nucl.Phys. A116, 196 (1968) 825 1451 790 [Li66] D. Lister and A. Sayres, Phys.Rev. 143, 745 (1966) 825 1451 791 [Lu70] B. Lundberg et al., Phys.Scripta 2, 273 (1970) 825 1451 792 [Ma62] J.P. Martin and M.S. Zucker, B.Am.Phys.Soc. 7, 72 (1962) 825 1451 793 [Ma68] D.R. Maxson and R.D. Murphy, Nucl.Phys. A110, 555 (1968) 825 1451 794 [Mc66a] W.J. McDonald et al., Nucl.Phys. 75, 353 (1966) 825 1451 795 [Mc66b] W.N. McDicken and W. Jack, Nucl.Phys. 88, 457 (1966) 825 1451 796 [Ne72] D.O. Nellis and P.S. Buchanan, report DNA-2716 (1972) 825 1451 797 [Ne90] R. Nelson et al., LANL, private communication, 1990 825 1451 798 [Ne99] R.O. Nelson and A. Michaudon, Los Alamos report LA-UR-99- 825 1451 799 4170 (1999). 825 1451 800 [No78] C. Nordborg et al., Nucl.Sci.Eng. 66, 75 (1978) 825 1451 801 [Ok55] A. Okazaki, Phys.Rev. 99, 55 (1955) 825 1451 802 [Ol90] N. Olsson et al., Nucl.Phys.A 509, 161 (1990) 825 1451 803 [Or70] V.J. Orphan et al., Nucl.Sci.Eng. 42, 352 (1970) 825 1451 804 [Pe72] F.G. Perey et al., report ORNL-4823 [ENDF-178] (1972) 825 1451 805 [Pe85] J.S. Petler et al., Phys.Rev.C 32, 673 (1985) 825 1451 806 [Ph61] D.D. Phillips, private communication to BNL (1961) 825 1451 807 [Sa97] T. Sanami and M. Baba, Trieste Conf.(1997)p.616 825 1451 808 [Sc72] R.A. Schrack, Bull.Am.Phy.Soc. 17, 555 [HE1] (1972) 825 1451 809 [Sc77] I. Schouky et al., report KFK-2503 825 1451 810 [Si68] I. Sick et al., Helv.Phys.Acta 41, 573 (1968) 825 1451 811 [Su94] T.S. Subramanian et al., Phys. Rev. C 34, 1580 (1986), and 825 1451 812 private communication to Chadwick (1994). 825 1451 813 [Wa57] R.B.Walton et al., Phys. Rev. 107, 1065 (1957) 825 1451 814 [Yo01] P.G. Young, G.M. Hale, and M.B. Chadwick, LANL report to 825 1451 815 be issued (2001). 825 1451 816 [Yo92] P.G. Young, E.D. Arthur, and M.B. Chadwick, Los Alamos 825 1451 817 report LA-12343-MS (1992) 825 1451 818 825 1451 819 ************************ C O N T E N T S *********************** 825 1451 820 ***************** Program LINEAR (VERSION 2004-1) *************** 825 1451 821 For All Data Greater than 1.0000E-10 barns in Absolute Value 825 1451 822 Data Linearized to Within an Accuracy of .100000000 per-cent 825 1451 823 ***************** Program FIXUP (Version 2004-1) **************** 825 1451 824 Corrected ZA/AWR in All Sections-----------------------------Yes 825 1451 825 Corrected Thresholds-----------------------------------------No 825 1451 826 Extended Cross Sections to 20 MeV----------------------------No 825 1451 827 Allow Cross Section Deletion---------------------------------No 825 1451 828 Allow Cross Section Reconstruction---------------------------Yes 825 1451 829 Make All Cross Sections Non-Negative-------------------------Yes 825 1451 830 Delete Energies Not in Ascending Order-----------------------Yes 825 1451 831 Deleted Duplicate Points-------------------------------------Yes 825 1451 832 Check for Ascending MAT/MF/MT Order--------------------------Yes 825 1451 833 Check for Legal MF/MT Numbers--------------------------------Yes 825 1451 834 Allow Creation of Missing Sections---------------------------No 825 1451 835 Allow Insertion of Energy Points-----------------------------No 825 1451 836 Create Uniform Energy Grid-----------------------------------No 825 1451 837 Delete Section if Cross Section =0 at All Energies-----------Yes 825 1451 838 **************** Program DICTIN (VERSION 2004-1) **************** 825 1451 839 1 451 983 3 825 1451 840 2 151 4 3 825 1451 841 3 1 1055 3 825 1451 842 3 2 474 3 825 1451 843 3 3 830 3 825 1451 844 3 4 97 3 825 1451 845 3 5 12 3 825 1451 846 3 16 16 3 825 1451 847 3 22 30 3 825 1451 848 3 23 25 3 825 1451 849 3 28 31 3 825 1451 850 3 32 14 3 825 1451 851 3 41 12 3 825 1451 852 3 44 12 3 825 1451 853 3 45 12 3 825 1451 854 3 51 47 3 825 1451 855 3 52 85 3 825 1451 856 3 53 82 3 825 1451 857 3 54 80 3 825 1451 858 3 55 67 3 825 1451 859 3 56 32 3 825 1451 860 3 57 31 3 825 1451 861 3 91 34 3 825 1451 862 3 102 114 3 825 1451 863 3 103 60 3 825 1451 864 3 104 55 3 825 1451 865 3 105 38 3 825 1451 866 3 107 689 3 825 1451 867 3 108 30 3 825 1451 868 3 112 19 3 825 1451 869 3 600 52 3 825 1451 870 3 601 42 3 825 1451 871 3 602 53 3 825 1451 872 3 603 53 3 825 1451 873 3 650 33 3 825 1451 874 3 651 26 3 825 1451 875 3 652 26 3 825 1451 876 3 653 23 3 825 1451 877 3 654 23 3 825 1451 878 3 655 21 3 825 1451 879 3 656 22 3 825 1451 880 3 657 14 3 825 1451 881 3 658 20 3 825 1451 882 3 659 14 3 825 1451 883 3 660 19 3 825 1451 884 3 661 20 3 825 1451 885 3 662 17 3 825 1451 886 3 663 18 3 825 1451 887 3 664 16 3 825 1451 888 3 665 16 3 825 1451 889 3 666 14 3 825 1451 890 3 667 15 3 825 1451 891 3 668 16 3 825 1451 892 3 669 14 3 825 1451 893 3 700 30 3 825 1451 894 3 701 27 3 825 1451 895 3 702 20 3 825 1451 896 3 703 15 3 825 1451 897 3 704 20 3 825 1451 898 3 705 16 3 825 1451 899 3 706 18 3 825 1451 900 3 707 16 3 825 1451 901 3 708 14 3 825 1451 902 3 709 16 3 825 1451 903 3 749 6 3 825 1451 904 3 800 639 3 825 1451 905 3 801 104 3 825 1451 906 3 802 87 3 825 1451 907 3 803 107 3 825 1451 908 4 2 3867 3 825 1451 909 4 51 84 3 825 1451 910 4 52 84 3 825 1451 911 4 53 66 3 825 1451 912 4 54 64 3 825 1451 913 4 55 50 3 825 1451 914 4 56 2 3 825 1451 915 4 57 2 3 825 1451 916 4 600 2 3 825 1451 917 4 601 2 3 825 1451 918 4 602 2 3 825 1451 919 4 603 2 3 825 1451 920 4 650 2 3 825 1451 921 4 651 2 3 825 1451 922 4 652 2 3 825 1451 923 4 653 2 3 825 1451 924 4 654 2 3 825 1451 925 4 655 2 3 825 1451 926 4 656 2 3 825 1451 927 4 657 2 3 825 1451 928 4 658 2 3 825 1451 929 4 659 2 3 825 1451 930 4 660 2 3 825 1451 931 4 661 2 3 825 1451 932 4 662 2 3 825 1451 933 4 663 2 3 825 1451 934 4 664 2 3 825 1451 935 4 665 2 3 825 1451 936 4 666 2 3 825 1451 937 4 667 2 3 825 1451 938 4 668 2 3 825 1451 939 4 669 2 3 825 1451 940 4 700 2 3 825 1451 941 4 701 2 3 825 1451 942 4 702 2 3 825 1451 943 4 703 2 3 825 1451 944 4 704 2 3 825 1451 945 4 705 2 3 825 1451 946 4 706 2 3 825 1451 947 4 707 2 3 825 1451 948 4 708 2 3 825 1451 949 4 709 2 3 825 1451 950 4 800 2188 3 825 1451 951 4 801 2 3 825 1451 952 4 802 2 3 825 1451 953 4 803 2 3 825 1451 954 6 5 4784 3 825 1451 955 6 16 522 3 825 1451 956 6 22 2279 3 825 1451 957 6 23 915 3 825 1451 958 6 28 1451 3 825 1451 959 6 32 476 3 825 1451 960 6 41 258 3 825 1451 961 6 44 246 3 825 1451 962 6 45 275 3 825 1451 963 6 91 2341 3 825 1451 964 6 108 798 3 825 1451 965 6 112 454 3 825 1451 966 6 749 320 3 825 1451 967 12 102 16 3 825 1451 968 13 4 1251 3 825 1451 969 13 16 134 3 825 1451 970 13 22 51 3 825 1451 971 13 103 286 3 825 1451 972 13 104 1540 3 825 1451 973 13 105 472 3 825 1451 974 13 107 1161 3 825 1451 975 14 4 933 3 825 1451 976 14 16 17 3 825 1451 977 14 22 187 3 825 1451 978 14 102 1 3 825 1451 979 14 103 554 3 825 1451 980 14 104 242 3 825 1451 981 14 105 1 3 825 1451 982 14 107 400 3 825 1451 983 825 1 0 984 825 0 0 985 8.01600E+3 1.58575E+1 0 0 1 0 825 2151 986 8.016000+3 1.000000+0 0 0 1 0 825 2151 987 1.000000-5 2.000000+7 0 0 0 0 825 2151 988 0.000000+0 5.562563-1 0 0 0 0 825 2151 989 825 2 0 990 825 0 0 991 8.01600E+3 1.58575E+1 0 0 0 0 825 3 1 992 0.0 0.0 0 0 1 3156 825 3 1 993 3156 2 825 3 1 994 1.00000E-5 3.85199983 1.09051E-5 3.85193405 1.21607E-5 3.85191958 825 3 1 995 1.33221E-5 3.85196873 1.47465E-5 3.85209284 1.48080E-5 3.85210074 825 3 1 996 1.58010E-5 3.85180687 1.63750E-5 3.85210176 1.67440E-5 3.85230258 825 3 1 997 1.75872E-5 3.85187336 1.77340E-5 3.85180216 1.91611E-5 3.85218043 825 3 1 998 1.95890E-5 3.85230380 2.08855E-5 3.85203721 2.16010E-5 3.85190434 825 3 1 999 2.26528E-5 3.85193502 2.51417E-5 3.85205581 2.66442E-5 3.85215099 825 3 1 1000 2.73450E-5 3.85220448 2.93360E-5 3.85200084 2.94929E-5 3.85198999 825 3 1 1001 3.27499E-5 3.85181226 3.51745E-5 3.85170608 3.83221E-5 3.85159499 825 3 1 1002 4.17709E-5 3.85150160 4.53055E-5 3.85143078 5.02833E-5 3.85136510 825 3 1 1003 5.32883E-5 3.85134121 5.89856E-5 3.85132202 6.54997E-5 3.85133369 825 3 1 1004 7.03489E-5 3.85136085 7.66442E-5 3.85141503 8.35419E-5 3.85149443 825 3 1 1005 9.06110E-5 3.85159340 .000100566 3.85175686 .000106576 3.85186668 825 3 1 1006 .000117971 3.85209336 .000118280 3.85210008 .000125820 3.85200290 825 3 1 1007 .000131000 3.85199837 .000140698 3.85200294 .000153288 3.85202225 825 3 1 1008 .000167084 3.85205757 .000179600 3.85210063 .000181222 3.85208935 825 3 1 1009 .000195620 3.85200151 .000201133 3.85200794 .000213153 3.85202981 825 3 1 1010 .000235942 3.85208436 .000241620 3.85210161 .000257500 3.85200142 825 3 1 1011 .000261998 3.85200205 .000281395 3.85201399 .000306576 3.85203896 825 3 1 1012 .000334167 3.85207632 .000349170 3.85210131 .000362444 3.85205760 825 3 1 1013 .000381250 3.85200135 .000402266 3.85201026 .000426306 3.85202602 825 3 1 1014 .000471885 3.85206514 .000505000 3.85210111 .000523998 3.85206654 825 3 1 1015 .000562792 3.85200249 .000564050 3.85200058 .000613153 3.85207522 825 3 1 1016 .000628750 3.85210093 .000668335 3.85203277 .000688310 3.85200057 825 3 1 1017 .000724889 3.85202707 .000804532 3.85209328 .000812410 3.85210048 825 3 1 1018 .000852612 3.85203658 .000876250 3.85200070 .000943770 3.85200886 825 3 1 1019 .001047995 3.85202985 .001125583 3.85205009 .001226307 3.85208110 825 3 1 1020 .001281800 3.85210071 .001336670 3.85204338 .001379700 3.85200010 825 3 1 1021 .001449778 3.85203546 .001569500 3.85210042 .001609065 3.85207853 825 3 1 1022 .001705226 3.85202811 .001759400 3.85200108 .001887541 3.85200807 825 3 1 1023 .002095992 3.85202537 .002251166 3.85204151 .002452614 3.85206582 825 3 1 1024 .002673341 3.85209599 .002703000 3.85210045 .002899555 3.85204769 825 3 1 1025 .003083400 3.85200079 .003218129 3.85199101 .003410451 3.85197901 825 3 1 1026 .003775082 3.85195952 .004191983 3.85194145 .004502332 3.85193030 825 3 1 1027 .004905227 3.85191819 .005346681 3.85190743 .005799109 3.85189861 825 3 1 1028 .006436256 3.85188918 .006820899 3.85188489 .007550161 3.85187905 825 3 1 1029 .008383964 3.85187535 .009004663 3.85187423 .009810454 3.85187444 825 3 1 1030 .010693363 3.85187645 .011598218 3.85188006 .012872514 3.85188728 825 3 1 1031 .013641800 3.85189262 .015100323 3.85190437 .016767928 3.85191992 825 3 1 1032 .018009326 3.85193264 .019620909 3.85195034 .021591241 3.85197346 825 3 1 1033 .023372171 3.85199547 .023741000 3.85200017 .024316988 3.85200002 825 3 1 1034 .025300000 3.85200000 .027589846 3.85199196 .030766577 3.85198232 825 3 1 1035 .033704840 3.85197465 .037308418 3.85196652 .041428573 3.85195855 825 3 1 1036 .044495698 3.85195336 .048477441 3.85194737 .052840253 3.85194160 825 3 1 1037 .057311509 3.85193639 .063608321 3.85193001 .067409678 3.85192660 825 3 1 1038 .074616834 3.85192087 .082857144 3.85191526 .088991395 3.85191160 825 3 1 1039 .096954882 3.85190739 .105680507 3.85190334 .114623019 3.85189968 825 3 1 1040 .127216643 3.85189521 .134819357 3.85189282 .149233669 3.85188881 825 3 1 1041 .165714290 3.85188489 .177982791 3.85188235 .193909764 3.85187942 825 3 1 1042 .211361014 3.85187660 .229246036 3.85187407 .254433284 3.85187098 825 3 1 1043 .269638713 3.85186934 .298467337 3.85186659 .331428580 3.85186392 825 3 1 1044 .355965582 3.85186220 .387819527 3.85186022 .422722027 3.85185834 825 3 1 1045 .458492073 3.85185665 .508866569 3.85185462 .539277427 3.85185355 825 3 1 1046 .596934674 3.85185178 .662857159 3.85185010 .711931164 3.85184902 825 3 1 1047 .775639053 3.85184782 .845444054 3.85184670 .916984147 3.85184572 825 3 1 1048 1.01773314 3.85184459 1.07855486 3.85184402 1.19386935 3.85184311 825 3 1 1049 1.32571432 3.85184232 1.42386233 3.85184185 1.55127811 3.85184139 825 3 1 1050 1.69088811 3.85184101 1.83396829 3.85184076 2.03546628 3.85184056 825 3 1 1051 2.15710971 3.85184053 2.38773870 3.85184058 2.65142863 3.85184082 825 3 1 1052 2.84772465 3.85184108 3.10255621 3.85184152 3.38177622 3.85184210 825 3 1 1053 3.66793658 3.85184278 4.07093256 3.85184386 4.31421943 3.85184457 825 3 1 1054 4.77547741 3.85184600 5.30285728 3.85184776 5.69544932 3.85184913 825 3 1 1055 6.20511243 3.85185098 6.76355243 3.85185307 7.33587316 3.85185528 825 3 1 1056 8.14186510 3.85185847 8.62843883 3.85186044 9.55095478 3.85186424 825 3 1 1057 10.6057145 3.85186866 11.3908986 3.85187200 12.4102249 3.85187638 825 3 1 1058 13.5271049 3.85188123 14.6717464 3.85188625 16.2837302 3.85189337 825 3 1 1059 17.2568777 3.85189770 19.1019096 3.85190595 21.2114290 3.85191544 825 3 1 1060 22.7817972 3.85192254 24.8204497 3.85193179 27.0542097 3.85194196 825 3 1 1061 29.3434926 3.85195242 32.5674604 3.85196718 34.5137554 3.85197611 825 3 1 1062 38.2038192 3.85199308 39.6630000 3.85199980 42.4228582 3.85198797 825 3 1 1063 45.5635945 3.85197454 49.6408994 3.85195711 54.1084194 3.85193805 825 3 1 1064 58.6869852 3.85191853 63.0850000 3.85189981 65.1349208 3.85189988 825 3 1 1065 69.0275107 3.85190002 76.4076383 3.85190031 78.7010000 3.85190041 825 3 1 1066 84.8457162 3.85188748 91.1271889 3.85187427 99.2817988 3.85185715 825 3 1 1067 108.216839 3.85183841 117.373971 3.85181921 130.269842 3.85179220 825 3 1 1068 138.055022 3.85177590 152.815277 3.85174502 169.691433 3.85170973 825 3 1 1069 182.254378 3.85168347 198.563598 3.85164940 216.433678 3.85161207 825 3 1 1070 234.747942 3.85157383 260.539684 3.85151999 276.110043 3.85148750 825 3 1 1071 305.630553 3.85142590 339.382865 3.85135548 364.508755 3.85130307 825 3 1 1072 397.127195 3.85123504 432.867356 3.85116051 469.495882 3.85108413 825 3 1 1073 521.079367 3.85097658 552.220086 3.85091166 611.261107 3.85078857 825 3 1 1074 678.765731 3.85064786 729.017512 3.85054311 794.254391 3.85040714 825 3 1 1075 865.734712 3.85025816 938.991765 3.85010548 1042.15873 3.84989047 825 3 1 1076 1104.44017 3.84976067 1222.52221 3.84951459 1357.53145 3.84923324 825 3 1 1077 1458.03502 3.84902380 1588.50878 3.84875191 1731.46942 3.84845400 825 3 1 1078 1877.98352 3.84814869 2084.31746 3.84771874 2208.88034 3.84745918 825 3 1 1079 2445.04443 3.84696707 2715.06293 3.84640443 2916.07005 3.84598559 825 3 1 1080 3177.01757 3.84544185 3462.93885 3.84484608 3755.96706 3.84423551 825 3 1 1081 4168.63494 3.84337564 4417.76069 3.84285655 4890.08886 3.84187238 825 3 1 1082 5430.12585 3.84074713 5832.14010 3.83990947 6354.03513 3.83882203 825 3 1 1083 6925.87769 3.83763052 7511.93412 3.83640939 8337.26989 3.83468970 825 3 1 1084 8835.52138 3.83365152 9780.17772 3.83168321 10860.2517 3.82943275 825 3 1 1085 11664.2802 3.82775745 12708.0702 3.82558259 13851.7554 3.82319959 825 3 1 1086 15023.8682 3.82075735 16674.5397 3.81731798 17671.0427 3.81524165 825 3 1 1087 19560.3554 3.81130505 21720.5034 3.80680413 23328.5604 3.80345356 825 3 1 1088 25416.1405 3.79910385 27703.5108 3.79433786 30047.7365 3.78945340 825 3 1 1089 33349.0795 3.78257468 35342.0855 3.77842203 39120.7108 3.77054884 825 3 1 1090 43441.0067 3.76154702 46657.1207 3.75484589 50832.2810 3.74614648 825 3 1 1091 55407.0215 3.73661450 60095.4729 3.72684559 66698.1589 3.71308816 825 3 1 1092 70684.1709 3.70478286 78241.4216 3.68903650 86882.0135 3.67103287 825 3 1 1093 93314.2415 3.65763061 100000.000 3.64370010 101664.562 3.64078156 825 3 1 1094 110814.043 3.62473947 120190.946 3.60829863 133396.319 3.58514520 825 3 1 1095 141368.343 3.57116759 156482.844 3.54466682 173764.027 3.51436715 825 3 1 1096 175000.000 3.51220007 186628.483 3.49721225 203329.124 3.47568697 825 3 1 1097 220000.000 3.45420006 221628.086 3.45287317 240000.000 3.43790006 825 3 1 1098 240381.892 3.43777595 260000.000 3.43140006 266792.637 3.43428693 825 3 1 1099 280000.000 3.43990006 282736.685 3.44441559 300000.000 3.47290006 825 3 1 1100 310000.000 3.50370005 312965.687 3.51704565 320000.000 3.54870005 825 3 1 1101 330000.000 3.61320005 340000.000 3.70560005 347528.054 3.80609957 825 3 1 1102 350000.000 3.83910005 360000.000 4.03510005 370000.000 4.33010005 825 3 1 1103 373256.966 4.47959479 380000.000 4.78910005 390000.000 5.53350005 825 3 1 1104 400000.000 6.79390005 405000.000 7.73810005 406658.248 8.14941188 825 3 1 1105 410000.000 8.97830005 415000.000 10.5680000 420000.000 12.4820000 825 3 1 1106 425000.000 14.4910000 430000.000 16.0630000 435000.000 16.5580000 825 3 1 1107 440000.000 15.7640000 443256.172 14.6829509 445000.000 14.1040000 825 3 1 1108 450000.000 12.2050000 455000.000 10.4700000 460000.000 9.03920004 825 3 1 1109 465000.000 7.90970004 470000.000 7.03100004 475000.000 6.34680004 825 3 1 1110 480000.000 5.80980004 480763.784 5.74467982 485000.000 5.38350004 825 3 1 1111 490000.000 5.04090004 495000.000 4.76200004 500000.000 4.53220004 825 3 1 1112 510000.000 4.17910004 520000.000 3.92340004 530000.000 3.73140004 825 3 1 1113 533585.272 3.67801534 540000.000 3.58250004 550000.000 3.46380004 825 3 1 1114 560000.000 3.36710004 565473.368 3.32298469 570000.000 3.28650004 825 3 1 1115 580000.000 3.21820004 590000.000 3.15940004 600000.000 3.10810004 825 3 1 1116 620000.000 3.02240004 625931.373 3.00187749 640000.000 2.95320004 825 3 1 1117 660000.000 2.89580004 680000.000 2.84770004 695056.108 2.81721142 825 3 1 1118 700000.000 2.80720004 720000.000 2.77380004 740000.000 2.74750004 825 3 1 1119 746513.932 2.74147465 760000.000 2.72900003 780000.000 2.71990003 825 3 1 1120 800000.000 2.72300003 813316.496 2.73631653 820000.000 2.74300003 825 3 1 1121 840000.000 2.78770003 860000.000 2.87050003 880000.000 3.01490003 825 3 1 1122 886512.344 3.09601128 900000.000 3.26400003 910000.000 3.45060003 825 3 1 1123 920000.000 3.69760003 930000.000 4.02520003 940000.000 4.45800003 825 3 1 1124 950000.000 5.02110003 960000.000 5.72720003 961527.567 5.84647032 825 3 1 1125 970000.000 6.50798603 980000.000 7.36410003 990000.000 7.96990003 825 3 1 1126 1000000.00 8.15400003 1010000.00 7.87030003 1020000.00 7.26740003 825 3 1 1127 1030000.00 6.55130003 1040000.00 5.86530003 1050000.00 5.27120003 825 3 1 1128 1060000.00 4.78050003 1067170.54 4.49532765 1070000.00 4.38280003 825 3 1 1129 1080000.00 4.06160003 1090000.00 3.80130003 1100000.00 3.58860003 825 3 1 1130 1110000.00 3.41383903 1120000.00 3.26760003 1130000.00 3.14495103 825 3 1 1131 1130946.74 3.13521371 1140000.00 3.04210003 1150000.00 2.95471303 825 3 1 1132 1160000.00 2.88000003 1170000.00 2.81727603 1180000.00 2.76430003 825 3 1 1133 1190000.00 2.72191403 1200000.00 2.68860003 1210000.00 2.66683003 825 3 1 1134 1220000.00 2.65790003 1230000.00 2.66740103 1240000.00 2.69860003 825 3 1 1135 1250000.00 2.76820003 1251862.75 2.79252754 1260000.00 2.89880003 825 3 1 1136 1270000.00 3.13680003 1280000.00 3.57260003 1285000.00 3.91240003 825 3 1 1137 1290000.00 4.36590003 1295000.00 4.94760003 1300000.00 5.62880003 825 3 1 1138 1305000.00 6.28690003 1310000.00 6.69960003 1315000.00 6.68200003 825 3 1 1139 1320000.00 6.26620003 1330000.00 5.03800003 1340000.00 4.07280003 825 3 1 1140 1350000.00 3.46760003 1360000.00 3.09040003 1370000.00 2.84410003 825 3 1 1141 1380000.00 2.67420003 1390000.00 2.55090003 1390112.22 2.54984965 825 3 1 1142 1400000.00 2.45730003 1450000.00 2.19410003 1493027.87 2.07603155 825 3 1 1143 1500000.00 2.05690002 1550000.00 1.96130002 1600000.00 1.89020002 825 3 1 1144 1620000.00 1.88030002 1626632.99 1.89495893 1630000.00 1.90240002 825 3 1 1145 1640000.00 2.06830002 1642000.00 2.18760002 1643000.00 2.28340002 825 3 1 1146 1644000.00 2.42190002 1645000.00 2.63060002 1646000.00 2.96150002 825 3 1 1147 1647000.00 3.51750002 1648000.00 4.50050002 1648500.00 5.25010002 825 3 1 1148 1649000.00 6.21370002 1649500.00 7.33920002 1650000.00 8.38890002 825 3 1 1149 1650500.00 8.92820002 1651000.00 8.64640002 1651500.00 7.71500002 825 3 1 1150 1652000.00 6.57920002 1653000.00 4.73330002 1654000.00 3.64930002 825 3 1 1151 1655000.00 3.03680002 1656000.00 2.67370002 1657000.00 2.44530002 825 3 1 1152 1658000.00 2.29370002 1659000.00 2.18850002 1660000.00 2.11250002 825 3 1 1153 1665000.00 1.92910002 1670000.00 1.86110002 1675000.00 1.82640002 825 3 1 1154 1682000.00 1.79710902 1685000.00 1.78880002 1686000.00 1.80701802 825 3 1 1155 1687000.00 1.85479102 1688000.00 1.91392002 1689000.00 1.96439502 825 3 1 1156 1690000.00 1.98430002 1691000.00 1.95887302 1694000.00 1.78795802 825 3 1 1157 1695000.00 1.76550002 1720000.00 1.72280002 1760000.00 1.66060002 825 3 1 1158 1773024.69 1.63722070 1780000.00 1.62470002 1800000.00 1.57920002 825 3 1 1159 1820000.00 1.56970002 1822000.00 1.60560002 1824000.00 1.68320002 825 3 1 1160 1826000.00 1.85300002 1828000.00 2.23930002 1830000.00 3.09640002 825 3 1 1161 1831000.00 3.74630002 1832000.00 4.38690002 1833000.00 4.73650002 825 3 1 1162 1834000.00 4.65670002 1835000.00 4.29630002 1836000.00 3.86850002 825 3 1 1163 1837000.00 3.48560002 1838000.00 3.17630002 1839000.00 2.93460002 825 3 1 1164 1840000.00 2.74660002 1842000.00 2.48270002 1844000.00 2.31270002 825 3 1 1165 1846000.00 2.19750002 1848000.00 2.11620002 1850000.00 2.05680002 825 3 1 1166 1852000.00 2.01260002 1854000.00 1.97920002 1856000.00 1.95390002 825 3 1 1167 1858000.00 1.93510002 1860000.00 1.92150002 1865000.00 1.90650002 825 3 1 1168 1870000.00 1.91610002 1875000.00 1.95320002 1880000.00 2.02830002 825 3 1 1169 1885000.00 2.16150002 1890000.00 2.38310002 1895000.00 2.71280002 825 3 1 1170 1900000.00 3.06600002 1905000.00 3.18230002 1910000.00 2.95930002 825 3 1 1171 1915000.00 2.62480002 1920000.00 2.34760002 1923055.13 2.22790003 825 3 1 1172 1925000.00 2.15170002 1930000.00 2.01670002 1935000.00 1.92170002 825 3 1 1173 1940000.00 1.85270002 1950000.00 1.76020002 1960000.00 1.70120002 825 3 1 1174 1970000.00 1.65940002 1980000.00 1.62750002 1990000.00 1.60160002 825 3 1 1175 2000000.00 1.57950002 2050000.00 1.49510002 2100000.00 1.42200002 825 3 1 1176 2134341.09 1.36492513 2150000.00 1.33890002 2200000.00 1.22050002 825 3 1 1177 2220000.00 1.15210002 2240000.00 1.06240002 2260000.00 .941440020 825 3 1 1178 2261893.48 .925895496 2280000.00 .777250020 2300000.00 .563260020 825 3 1 1179 2305000.00 .503500020 2315000.00 .381960020 2321000.00 .311500020 825 3 1 1180 2324000.00 .278180020 2327000.00 .246710020 2329000.00 .226980020 825 3 1 1181 2331000.00 .208410020 2333000.00 .191140020 2334000.00 .183030020 825 3 1 1182 2335000.00 .175290020 2336000.00 .167930020 2337000.00 .160970020 825 3 1 1183 2338000.00 .154420020 2339000.00 .148300020 2340000.00 .142610020 825 3 1 1184 2341000.00 .137370020 2342000.00 .132590020 2343000.00 .128280020 825 3 1 1185 2344000.00 .124430020 2345000.00 .121070020 2346000.00 .118200020 825 3 1 1186 2347000.00 .115820020 2348000.00 .113930020 2349000.00 .112530020 825 3 1 1187 2350000.00 .111640020 2351000.00 .111240020 2352000.00 .111330020 825 3 1 1188 2353000.00 .111920020 2354170.00 .113224520 2355319.00 .115171431 825 3 1 1189 2355357.00 .115235820 2357000.00 .119090020 2358000.00 .122060020 825 3 1 1190 2359000.00 .125480020 2360000.00 .129330020 2361000.00 .133620020 825 3 1 1191 2362000.00 .138330020 2363000.00 .143440020 2364000.00 .148940020 825 3 1 1192 2365000.00 .154820020 2366000.00 .161060020 2368000.00 .174570020 825 3 1 1193 2370000.00 .189340020 2375000.00 .230970020 2380000.00 .277670020 825 3 1 1194 2400000.00 .480700020 2400191.36 .482514112 2400382.36 .484324792 825 3 1 1195 2400573.00 .486132060 2400763.29 .487936009 2400953.22 .489736545 825 3 1 1196 2401142.80 .491533764 2401332.02 .493327569 2401520.89 .495118057 825 3 1 1197 2401709.40 .496905132 2401897.56 .498688888 2402085.36 .500469232 825 3 1 1198 2402272.81 .502246258 2402459.91 .504019966 2402646.66 .505790356 825 3 1 1199 2402833.06 .507557428 2403019.11 .509321182 2403204.81 .511081618 825 3 1 1200 2403390.16 .512838736 2403575.16 .514592536 2403759.82 .516343113 825 3 1 1201 2403944.13 .518090372 2404128.09 .519834313 2404311.71 .521575030 825 3 1 1202 2404494.98 .523312430 2404677.91 .525046606 2404860.50 .526777560 825 3 1 1203 2405042.74 .528505195 2405224.64 .530229607 2405406.20 .531950796 825 3 1 1204 2405587.42 .533668761 2405768.30 .535383504 2405948.84 .537095023 825 3 1 1205 2406129.04 .538803319 2406308.90 .540508392 2406488.42 .542210241 825 3 1 1206 2406667.61 .543908962 2406846.46 .545604460 2407024.97 .547296735 825 3 1 1207 2407203.15 .548985881 2407380.99 .550671805 2407558.50 .552354599 825 3 1 1208 2407735.67 .554034171 2407912.51 .555710614 2408089.02 .557383929 825 3 1 1209 2408265.20 .559054115 2408441.05 .560721173 2408616.57 .562385103 825 3 1 1210 2408791.75 .564045809 2408966.61 .565703482 2409141.14 .567358027 825 3 1 1211 2409315.34 .569009443 2409489.21 .570657730 2409662.75 .572302889 825 3 1 1212 2409835.97 .573945015 2410000.00 .575500019 2410008.86 .575574603 825 3 1 1213 2410181.43 .577027297 2410353.67 .578477214 2410525.59 .579924436 825 3 1 1214 2410697.18 .581368881 2410868.45 .582810632 2411039.40 .584249689 825 3 1 1215 2411210.03 .585686052 2411380.34 .587119722 2411550.33 .588550697 825 3 1 1216 2411720.00 .589978979 2411889.35 .591404568 2412058.38 .592827462 825 3 1 1217 2412227.09 .594247663 2412395.48 .595665170 2412563.55 .597079983 825 3 1 1218 2412731.31 .598492187 2412898.75 .599901697 2413065.88 .601308597 825 3 1 1219 2413232.69 .602712804 2413399.19 .604114401 2413565.37 .605513304 825 3 1 1220 2413731.24 .606909598 2413896.80 .608303282 2414062.04 .609694272 825 3 1 1221 2414226.97 .611082653 2414391.59 .612468424 2414555.90 .613851586 825 3 1 1222 2414719.90 .615232138 2414883.59 .616610080 2415046.97 .617985413 825 3 1 1223 2415210.05 .619358220 2415372.82 .620728418 2415535.28 .622096007 825 3 1 1224 2415697.43 .623460985 2415859.28 .624823439 2416020.82 .626183282 825 3 1 1225 2416182.06 .627540601 2416342.99 .628895309 2416503.62 .630247493 825 3 1 1226 2416663.95 .631597151 2416823.98 .632944283 2416983.70 .634288806 825 3 1 1227 2417143.12 .635630804 2417302.24 .636970276 2417461.06 .638307223 825 3 1 1228 2417619.58 .639641644 2417777.80 .640973540 2417935.72 .642302910 825 3 1 1229 2418093.34 .643629756 2418250.67 .644954160 2418407.70 .646276038 825 3 1 1230 2418564.43 .647595391 2418720.87 .648912303 2418877.01 .650226690 825 3 1 1231 2419032.85 .651538551 2419188.40 .652847971 2419343.67 .654155034 825 3 1 1232 2419498.64 .655459571 2419653.32 .656761667 2419807.71 .658061322 825 3 1 1233 2419961.81 .659358536 2420000.00 .659680019 2420115.61 .660519348 825 3 1 1234 2420269.12 .661633831 2420422.34 .662746208 2420575.27 .663856480 825 3 1 1235 2420727.91 .664964646 2420880.26 .666070707 2421032.33 .667174735 825 3 1 1236 2421184.11 .668276658 2421335.60 .669376475 2421486.81 .670474260 825 3 1 1237 2421637.73 .671569939 2421788.37 .672663586 2421938.72 .673755127 825 3 1 1238 2422088.79 .674844635 2422238.57 .675932038 2422388.07 .677017408 825 3 1 1239 2422537.29 .678100745 2422686.22 .679181977 2422834.87 .680261176 825 3 1 1240 2422983.24 .681338342 2423131.33 .682413475 2423279.14 .683486576 825 3 1 1241 2423426.67 .684557644 2423573.92 .685626679 2423720.89 .686693681 825 3 1 1242 2423867.58 .687758650 2424013.99 .688821587 2424160.13 .689882563 825 3 1 1243 2424305.99 .690941507 2424524.23 .692525929 2424741.92 .694106359 825 3 1 1244 2424958.92 .695681779 2425175.38 .697253278 2425391.15 .698819768 825 3 1 1245 2425606.38 .700382338 2425820.92 .701939899 2426034.93 .703493611 825 3 1 1246 2426248.26 .705042387 2426461.05 .706587242 2426673.16 .708127161 825 3 1 1247 2426884.75 .709663304 2427095.66 .711194511 2427306.05 .712721942 825 3 1 1248 2427515.77 .714244510 2427724.96 .715763229 2427933.49 .717277157 825 3 1 1249 2428141.49 .718787237 2428348.83 .720292525 2428555.65 .721794038 825 3 1 1250 2428761.81 .723290760 2428967.46 .724783779 2429172.45 .726272006 825 3 1 1251 2429376.93 .727756531 2429580.75 .729236264 2429784.07 .730712368 825 3 1 1252 2429986.74 .732183752 2430000.00 .732280019 2430188.91 .733442383 825 3 1 1253 2430390.43 .734682335 2430591.44 .735919150 2430791.82 .737152088 825 3 1 1254 2430991.69 .738381888 2431190.93 .739607812 2431389.67 .740830659 825 3 1 1255 2431587.77 .742049568 2431785.37 .743265401 2431982.34 .744477357 825 3 1 1256 2432178.82 .745686299 2432374.68 .746891425 2432570.05 .748093537 825 3 1 1257 2432764.79 .749291772 2432959.04 .750486993 2433152.67 .751678398 825 3 1 1258 2433345.82 .752866850 2433538.35 .754051487 2433730.40 .755233171 825 3 1 1259 2433921.84 .756411101 2434112.79 .757586016 2434303.14 .758757240 825 3 1 1260 2434493.01 .759925510 2434682.28 .761090088 2434871.07 .762251713 825 3 1 1261 2435059.26 .763409646 2435246.97 .764564626 2435434.08 .765715914 825 3 1 1262 2435620.72 .766864310 2435806.76 .768009014 2435992.34 .769150887 825 3 1 1263 2436177.32 .770289069 2436361.85 .771424482 2436545.78 .772556204 825 3 1 1264 2436729.25 .773685095 2436912.13 .774810355 2437094.56 .775932847 825 3 1 1265 2437276.41 .777051770 2437457.80 .778167863 2437638.61 .779280387 825 3 1 1266 2437818.97 .780390142 2437998.75 .781496328 2438178.07 .782599684 825 3 1 1267 2438356.82 .783699533 2438535.12 .784796613 2438712.85 .785890185 825 3 1 1268 2438890.13 .786980989 2439066.85 .788068347 2439243.12 .789152937 825 3 1 1269 2439418.82 .790234019 2439594.09 .791312455 2439768.80 .792387446 825 3 1 1270 2439943.06 .793459668 2440000.00 .793810019 2440116.77 .794412903 825 3 1 1271 2440290.04 .795307496 2440462.76 .796199249 2440635.04 .797088731 825 3 1 1272 2440806.77 .797975373 2440978.06 .798859743 2441148.81 .799741325 825 3 1 1273 2441319.13 .800620688 2441488.91 .801497262 2441658.26 .802371616 825 3 1 1274 2441827.06 .803243130 2441995.44 .804112476 2442163.28 .804979034 825 3 1 1275 2442330.70 .805843423 2442497.58 .806705025 2442664.04 .807564458 825 3 1 1276 2442829.97 .808421154 2442995.48 .809275683 2443160.46 .810127474 825 3 1 1277 2443325.03 .810977149 2443489.07 .811824088 2443652.70 .812668909 825 3 1 1278 2443815.81 .813511046 2443978.50 .814351015 2444140.68 .815188350 825 3 1 1279 2444302.44 .816023517 2444463.69 .816856051 2444624.53 .817686468 825 3 1 1280 2444784.85 .818514200 2444944.77 .819339867 2445104.18 .820162901 825 3 1 1281 2445263.18 .820983818 2445421.67 .821802102 2445579.77 .822618372 825 3 1 1282 2445737.36 .823432009 2445894.56 .824243633 2445999.09 .824783321 825 3 1 1283 2446207.75 .825860633 2446415.61 .826933814 2446622.67 .828002865 825 3 1 1284 2446828.94 .829067837 2447034.43 .830128781 2447239.13 .831185648 825 3 1 1285 2447443.05 .832238486 2447646.19 .833287298 2447848.55 .834332083 825 3 1 1286 2448050.14 .835372892 2448250.95 .836409674 2448451.00 .837442532 825 3 1 1287 2448650.28 .838471415 2448848.80 .839496374 2449046.56 .840517409 825 3 1 1288 2449243.56 .841534520 2449439.81 .842547758 2449635.31 .843557125 825 3 1 1289 2449830.06 .844562619 2450000.00 .845440019 2450024.06 .845543694 825 3 1 1290 2450217.32 .846376451 2450409.84 .847206020 2450601.62 .848032400 825 3 1 1291 2450792.67 .848855634 2450982.99 .849675723 2451172.58 .850492667 825 3 1 1292 2451361.44 .851306464 2451549.58 .852117160 2451737.00 .852924752 825 3 1 1293 2451923.70 .853729243 2452109.69 .854530674 2452294.97 .855329045 825 3 1 1294 2452479.53 .856124314 2452663.39 .856916567 2452846.54 .857705760 825 3 1 1295 2453028.99 .858491937 2453210.74 .859275098 2453391.79 .860055242 825 3 1 1296 2453572.15 .860832414 2453751.82 .861606612 2453930.80 .862377837 825 3 1 1297 2454109.09 .863146088 2454286.70 .863911410 2454463.63 .864673801 825 3 1 1298 2454639.88 .865433262 2454815.45 .866189793 2454990.35 .866943437 825 3 1 1299 2455164.58 .867694195 2455338.14 .868442065 2455511.04 .869187091 825 3 1 1300 2455683.27 .869929230 2455854.84 .870668525 2456025.75 .871404976 825 3 1 1301 2456196.01 .872138626 2456365.62 .872869476 2456534.58 .873597525 825 3 1 1302 2456702.89 .874322772 2456870.55 .875045219 2457037.57 .875764908 825 3 1 1303 2457203.94 .876481797 2457369.68 .877195970 2457534.78 .877907386 825 3 1 1304 2457699.25 .878616088 2457863.08 .879322031 2458026.29 .880025303 825 3 1 1305 2458188.87 .880725860 2458350.82 .881423703 2458512.15 .882118874 825 3 1 1306 2458672.86 .882811373 2458832.95 .883501201 2458992.43 .884188400 825 3 1 1307 2459151.30 .884872971 2459309.56 .885554913 2459467.21 .886234227 825 3 1 1308 2459624.25 .886910913 2459780.70 .887585056 2459936.54 .888256570 825 3 1 1309 2460000.00 .888530019 2460091.79 .888859454 2460246.44 .889414492 825 3 1 1310 2460400.49 .889967378 2460553.95 .890518146 2460706.82 .891066796 825 3 1 1311 2460859.10 .891613329 2461010.80 .892157780 2461161.92 .892700150 825 3 1 1312 2461312.45 .893240402 2461462.40 .893778573 2461611.78 .894314698 825 3 1 1313 2461760.58 .894848741 2461908.81 .895380738 2462130.01 .896174625 825 3 1 1314 2462350.09 .896964492 2462568.75 .897749263 2462786.29 .898530014 825 3 1 1315 2463002.43 .899305741 2463217.48 .900077555 2463431.14 .900844381 825 3 1 1316 2463643.71 .901607294 2463854.91 .902365291 2464065.03 .903119412 825 3 1 1317 2464273.80 .903868687 2464481.50 .904614123 2464687.87 .905354785 825 3 1 1318 2464893.19 .906091678 2465097.18 .906823798 2465300.14 .907552222 825 3 1 1319 2465501.79 .908275944 2465702.41 .908995969 2465901.74 .909711364 825 3 1 1320 2466100.04 .910423063 2466297.08 .911130239 2466493.10 .911833755 825 3 1 1321 2466687.86 .912532749 2466881.63 .913228189 2467074.15 .913919144 825 3 1 1322 2467265.68 .914606545 2467455.98 .915289531 2467645.30 .915969001 825 3 1 1323 2467833.41 .916644128 2468020.55 .917315773 2468206.49 .917983112 825 3 1 1324 2468391.48 .918647041 2468575.28 .919306699 2468758.14 .919962984 825 3 1 1325 2468939.82 .920615033 2469120.57 .921263745 2469300.16 .921908293 825 3 1 1326 2469478.82 .922549504 2469656.33 .923186588 2469832.93 .923820405 825 3 1 1327 2470000.00 .924420019 2470008.40 .924445093 2470182.97 .924966185 825 3 1 1328 2470356.41 .925483903 2470528.97 .925998995 2470700.41 .926510743 825 3 1 1329 2470870.97 .927019865 2471040.43 .927525703 2471209.02 .928028944 825 3 1 1330 2471376.53 .928528961 2471543.18 .929026412 2471708.76 .929520668 825 3 1 1331 2471873.49 .930012387 2472037.15 .930500912 2472199.98 .930986960 825 3 1 1332 2472361.75 .931469843 2472522.70 .931950279 2472682.60 .932427580 825 3 1 1333 2472841.69 .932902464 2473052.72 .933532388 2473262.12 .934157447 825 3 1 1334 2473469.90 .934777671 2473676.07 .935393088 2473880.65 .936003759 825 3 1 1335 2474083.65 .936609714 2474285.08 .937210983 2474484.95 .937807595 825 3 1 1336 2474683.27 .938399580 2474880.06 .938986998 2475075.33 .939569879 825 3 1 1337 2475269.09 .940148253 2475461.35 .940722149 2475652.12 .941291597 825 3 1 1338 2475841.42 .941856658 2476029.25 .942417330 2476215.63 .942973675 825 3 1 1339 2476400.56 .943525691 2476584.06 .944073438 2476766.14 .944616947 825 3 1 1340 2476946.81 .945156247 2477126.08 .945691368 2477303.97 .946222370 825 3 1 1341 2477480.48 .946749252 2477655.63 .947272075 2477829.42 .947790838 825 3 1 1342 2478001.86 .948305571 2478172.97 .948816335 2478342.75 .949323128 825 3 1 1343 2478511.22 .949826011 2478678.38 .950324984 2478844.25 .950820105 825 3 1 1344 2479008.83 .951311377 2479172.14 .951798857 2479334.18 .952282546 825 3 1 1345 2479494.97 .952762505 2479654.51 .953238732 2479812.81 .953711257 825 3 1 1346 2479969.89 .954180141 2480000.00 .954270019 2480125.76 .954582533 825 3 1 1347 2480280.42 .954966863 2480433.88 .955348211 2480586.15 .955726602 825 3 1 1348 2480737.24 .956102061 2480887.16 .956474612 2481109.71 .957027649 825 3 1 1349 2481329.97 .957574995 2481547.38 .958115258 2481762.55 .958649956 825 3 1 1350 2481974.94 .959177745 2482185.14 .959700092 2482392.63 .960215705 825 3 1 1351 2482597.98 .960725999 2482800.68 .961229709 2483001.29 .961728225 825 3 1 1352 2483199.30 .962220280 2483395.28 .962707290 2483588.72 .963187988 825 3 1 1353 2483780.17 .963663742 2483969.14 .964133332 2484156.17 .964598102 825 3 1 1354 2484340.77 .965056833 2484523.47 .965510842 2484703.81 .965958987 825 3 1 1355 2484882.28 .966402485 2485058.45 .966840267 2485232.80 .967273527 825 3 1 1356 2485404.90 .967701196 2485575.22 .968124441 2485743.34 .968542219 825 3 1 1357 2485909.72 .968955673 2486073.95 .969363785 2486236.48 .969767672 825 3 1 1358 2486396.91 .970166341 2486555.68 .970560884 2486765.19 .971081516 825 3 1 1359 2486971.45 .971594072 2487174.50 .972098652 2487374.39 .972595378 825 3 1 1360 2487571.18 .973084401 2487764.90 .973565796 2487955.62 .974039735 825 3 1 1361 2488143.36 .974506269 2488328.19 .974965571 2488510.14 .975417717 825 3 1 1362 2488689.27 .975862855 2488865.60 .976301035 2489039.19 .976732406 825 3 1 1363 2489210.08 .977157068 2489378.31 .977575120 2489543.93 .977986685 825 3 1 1364 2489706.97 .978391840 2489867.47 .978790682 2490000.00 .979120019 825 3 1 1365 2490025.47 .979172717 2490181.02 .979494550 2490334.15 .979811376 825 3 1 1366 2490484.90 .980123277 2490706.91 .980582616 2490923.19 .981030099 825 3 1 1367 2491134.99 .981468313 2491341.32 .981895210 2491543.38 .982313272 825 3 1 1368 2491740.23 .982720555 2491933.00 .983119396 2492120.79 .983507934 825 3 1 1369 2492304.70 .983888443 2492483.85 .984259105 2492659.29 .984622090 825 3 1 1370 2492830.19 .984975682 2492997.56 .985321971 2493160.60 .985659301 825 3 1 1371 2493320.26 .985989637 2493528.73 .986420962 2493730.71 .986838858 825 3 1 1372 2493926.39 .987243720 2494115.96 .987635940 2494299.63 .988015954 825 3 1 1373 2494477.57 .988384111 2494649.96 .988740786 2494816.97 .989086330 825 3 1 1374 2494978.78 .989421115 2495135.54 .989745451 2495287.41 .990059670 825 3 1 1375 2495506.95 .990513899 2495715.19 .990944747 2495914.82 .991357782 825 3 1 1376 2496104.17 .991749547 2496285.68 .992125091 2496457.85 .992481311 825 3 1 1377 2496622.90 .992822799 2496833.84 .993259234 2497031.61 .993668420 825 3 1 1378 2497217.03 .994052054 2497390.87 .994411729 2497553.86 .994748955 825 3 1 1379 2497706.68 .995065140 2497917.11 .995500520 2498110.22 .995900064 825 3 1 1380 2498283.64 .996258870 2498442.77 .996588110 2498637.37 .996990738 825 3 1 1381 2498807.66 .997343068 2499026.21 .997795248 2499147.91 .998047045 825 3 1 1382 2499360.91 .998487742 2499580.57 .998942218 2499730.36 .999252134 825 3 1 1383 2499910.12 .999624057 2500000.00 .999810019 2500573.85 1.00071642 825 3 1 1384 2501144.83 1.00161828 2501712.23 1.00251449 2502276.81 1.00340624 825 3 1 1385 2502837.84 1.00429239 2503396.07 1.00517411 2503725.50 1.00569445 825 3 1 1386 2503950.80 1.00605031 2504502.76 1.00692213 2505051.26 1.00778848 825 3 1 1387 2505597.02 1.00865051 2506139.35 1.00950712 2506678.97 1.01035945 825 3 1 1388 2507215.20 1.01120643 2507748.75 1.01204917 2508456.63 1.01316727 825 3 1 1389 2509159.17 1.01427693 2509856.41 1.01537822 2510548.40 1.01647122 825 3 1 1390 2511235.17 1.01755597 2511916.76 1.01863254 2512593.21 1.01970099 825 3 1 1391 2513264.56 1.02076139 2513930.83 1.02181377 2514592.08 1.02285821 825 3 1 1392 2515248.33 1.02389476 2515899.63 1.02492348 2516546.01 1.02594444 825 3 1 1393 2517187.49 1.02695766 2517824.14 1.02796325 2518455.97 1.02896122 825 3 1 1394 2519083.01 1.02995163 2519705.31 1.03093456 2520000.00 1.03140002 825 3 1 1395 2520322.89 1.03175358 2520935.81 1.03242473 2521544.08 1.03309079 825 3 1 1396 2522147.75 1.03375181 2522746.84 1.03440781 2523341.39 1.03505884 825 3 1 1397 2523931.43 1.03570493 2524517.01 1.03634614 2525098.14 1.03698248 825 3 1 1398 2525674.87 1.03761400 2526247.22 1.03824072 2526815.22 1.03886268 825 3 1 1399 2527378.92 1.03947994 2527938.33 1.04009249 2528493.50 1.04070040 825 3 1 1400 2529044.45 1.04130369 2529591.22 1.04190240 2530133.83 1.04249656 825 3 1 1401 2530672.31 1.04308620 2531206.70 1.04367136 2531737.03 1.04425207 825 3 1 1402 2532263.32 1.04482835 2532785.62 1.04540027 2533303.94 1.04596783 825 3 1 1403 2533818.31 1.04653107 2534328.77 1.04709002 2535087.67 1.04792102 825 3 1 1404 2535836.94 1.04874147 2536578.63 1.04955362 2537310.90 1.05035545 825 3 1 1405 2538035.76 1.05114918 2538751.41 1.05193281 2539459.82 1.05270852 825 3 1 1406 2540000.00 1.05330002 2540159.22 1.05342023 2540851.54 1.05394293 825 3 1 1407 2541535.04 1.05445897 2542211.63 1.05496980 2542879.61 1.05547412 825 3 1 1408 2543540.80 1.05597332 2544193.58 1.05646617 2544839.72 1.05695401 825 3 1 1409 2545477.64 1.05743564 2546109.08 1.05791237 2546732.47 1.05838303 825 3 1 1410 2547349.53 1.05884891 2547958.72 1.05930885 2548561.71 1.05976411 825 3 1 1411 2549157.01 1.06021356 2549746.26 1.06065845 2550327.99 1.06109765 825 3 1 1412 2550903.80 1.06153239 2551472.26 1.06196158 2552034.94 1.06238640 825 3 1 1413 2552590.43 1.06280579 2553140.25 1.06322091 2553865.90 1.06376877 825 3 1 1414 2554580.42 1.06430824 2555283.96 1.06483941 2555976.70 1.06536243 825 3 1 1415 2556658.80 1.06587741 2557330.42 1.06638449 2557991.71 1.06688376 825 3 1 1416 2558642.84 1.06737536 2559283.96 1.06785941 2559915.22 1.06833601 825 3 1 1417 2560000.00 1.06840002 2560536.76 1.06867377 2561148.74 1.06898588 825 3 1 1418 2561751.30 1.06929318 2562344.59 1.06959576 2562928.74 1.06989368 825 3 1 1419 2563503.90 1.07018701 2564070.19 1.07047582 2564627.75 1.07076017 825 3 1 1420 2565176.72 1.07104015 2565717.23 1.07131581 2566249.40 1.07158721 825 3 1 1421 2566773.37 1.07185444 2567289.26 1.07211754 2568047.21 1.07250410 825 3 1 1422 2568789.64 1.07288274 2569513.04 1.07325167 2570221.61 1.07361304 825 3 1 1423 2570912.00 1.07396514 2571588.23 1.07431002 2572247.12 1.07464605 825 3 1 1424 2572892.47 1.07497518 2573521.27 1.07529587 2574137.15 1.07560997 825 3 1 1425 2574737.21 1.07591600 2575324.95 1.07621574 2575897.58 1.07650778 825 3 1 1426 2576458.44 1.07679382 2577185.15 1.07716445 2577895.07 1.07752650 825 3 1 1427 2578583.00 1.07787735 2579249.60 1.07821731 2579895.54 1.07854674 825 3 1 1428 2580000.00 1.07860002 2580521.45 1.07877470 2581127.94 1.07897788 825 3 1 1429 2581715.61 1.07917475 2582285.04 1.07936551 2582836.81 1.07955035 825 3 1 1430 2583371.44 1.07972945 2583889.46 1.07990299 2584638.42 1.08015389 825 3 1 1431 2585348.98 1.08039193 2586030.27 1.08062016 2586676.61 1.08083668 825 3 1 1432 2587296.32 1.08104429 2587884.23 1.08124124 2588447.89 1.08143006 825 3 1 1433 2589168.39 1.08167143 2589844.04 1.08189777 2590477.62 1.08211002 825 3 1 1434 2591071.75 1.08230906 2591628.87 1.08249569 2592396.18 1.08275274 825 3 1 1435 2593100.44 1.08298867 2593733.03 1.08320058 2594313.60 1.08339507 825 3 1 1436 2595023.72 1.08363296 2595645.24 1.08384117 2596189.19 1.08402340 825 3 1 1437 2596873.54 1.08425265 2597446.44 1.08444458 2598084.60 1.08465836 825 3 1 1438 2598768.51 1.08488747 2599384.18 1.08509372 2600000.00 1.08530002 825 3 1 1439 2601147.16 1.08546521 2602282.88 1.08562875 2603404.34 1.08579024 825 3 1 1440 2604514.61 1.08595012 2605610.92 1.08610799 2606696.29 1.08626428 825 3 1 1441 2607768.00 1.08641861 2608829.00 1.08657139 2609876.64 1.08672225 825 3 1 1442 2610913.79 1.08687160 2611937.89 1.08701907 2612951.72 1.08716507 825 3 1 1443 2614290.03 1.08735778 2615608.10 1.08754759 2616906.22 1.08773451 825 3 1 1444 2618184.69 1.08791861 2619443.79 1.08809992 2620683.81 1.08827849 825 3 1 1445 2621905.03 1.08845434 2623107.72 1.08862753 2624292.16 1.08879809 825 3 1 1446 2625458.61 1.08896606 2626607.34 1.08913148 2627738.62 1.08929438 825 3 1 1447 2628852.69 1.08945481 2629949.82 1.08961279 2631030.25 1.08976837 825 3 1 1448 2632094.23 1.08992159 2633142.01 1.09007247 2634173.83 1.09022105 825 3 1 1449 2635189.92 1.09036737 2636190.52 1.09051145 2637175.85 1.09065334 825 3 1 1450 2638146.15 1.09079306 2639101.63 1.09093065 2640505.74 1.09113285 825 3 1 1451 2641881.40 1.09133094 2643222.11 1.09152400 2644535.62 1.09171315 825 3 1 1452 2645815.74 1.09189749 2647069.85 1.09207808 2648292.04 1.09225407 825 3 1 1453 2649489.39 1.09242649 2650000.00 1.09250002 2650656.23 1.09250396 825 3 1 1454 2651799.33 1.09251081 2652913.28 1.09251750 2654004.56 1.09252405 825 3 1 1455 2655067.99 1.09253043 2656109.74 1.09253668 2657470.45 1.09254484 825 3 1 1456 2658789.30 1.09255275 2660067.56 1.09256042 2661306.47 1.09256786 825 3 1 1457 2662507.21 1.09257506 2663670.94 1.09258204 2664798.79 1.09258881 825 3 1 1458 2665891.85 1.09259537 2666951.18 1.09260173 2667977.80 1.09260789 825 3 1 1459 2668972.72 1.09261385 2670404.06 1.09262244 2671776.80 1.09263068 825 3 1 1460 2673079.43 1.09263850 2674328.66 1.09264599 2675514.05 1.09265310 825 3 1 1461 2676650.80 1.09265992 2677729.42 1.09266640 2678763.73 1.09267260 825 3 1 1462 2680086.09 1.09268054 2681326.40 1.09268798 2682489.70 1.09269496 825 3 1 1463 2683580.76 1.09270150 2684604.03 1.09270764 2686028.18 1.09271619 825 3 1 1464 2687307.72 1.09272386 2688482.32 1.09273091 2689200.73 1.09273522 825 3 1 1465 2690548.27 1.09274331 2691727.93 1.09275039 2692760.55 1.09275658 825 3 1 1466 2694059.96 1.09276438 2695147.98 1.09277091 2696360.17 1.09277818 825 3 1 1467 2697269.67 1.09278364 2698634.49 1.09279183 2700000.00 1.09280002 825 3 1 1468 2701548.65 1.09275046 2703049.76 1.09270243 2704504.75 1.09265587 825 3 1 1469 2705915.02 1.09261074 2707281.92 1.09256700 2709248.71 1.09250406 825 3 1 1470 2711135.33 1.09244369 2712925.93 1.09238639 2714643.41 1.09233143 825 3 1 1471 2716273.39 1.09227927 2717836.73 1.09222924 2719320.33 1.09218177 825 3 1 1472 2720743.19 1.09213624 2722562.59 1.09207802 2724269.38 1.09202340 825 3 1 1473 2725870.46 1.09197216 2727372.34 1.09192410 2728781.10 1.09187902 825 3 1 1474 2730742.08 1.09181627 2732504.26 1.09175988 2734122.16 1.09170811 825 3 1 1475 2735111.84 1.09167644 2736968.44 1.09161703 2738594.00 1.09156501 825 3 1 1476 2740017.16 1.09151947 2741808.28 1.09146215 2743308.26 1.09141416 825 3 1 1477 2744979.67 1.09136067 2746233.89 1.09132054 2748116.30 1.09126030 825 3 1 1478 2750000.00 1.09120002 2752299.46 1.09123221 2754505.43 1.09126310 825 3 1 1479 2756599.33 1.09129241 2758607.94 1.09132053 2760514.37 1.09134722 825 3 1 1480 2762343.03 1.09137282 2764078.56 1.09139712 2765743.18 1.09142043 825 3 1 1481 2767871.90 1.09145023 2769869.06 1.09147819 2771742.70 1.09150442 825 3 1 1482 2773500.40 1.09152903 2775149.26 1.09155211 2777444.65 1.09158425 825 3 1 1483 2779507.56 1.09161313 2780224.44 1.09162317 2781401.75 1.09163965 825 3 1 1484 2783647.29 1.09167109 2785686.15 1.09169963 2787471.38 1.09172463 825 3 1 1485 2789764.09 1.09175672 2791041.53 1.09177461 2793278.46 1.09180593 825 3 1 1486 2795587.17 1.09183825 2797162.39 1.09186030 2799053.81 1.09188679 825 3 1 1487 2800000.00 1.09190003 2802299.81 1.09229560 2804506.08 1.09267508 825 3 1 1488 2806600.25 1.09303528 2808609.08 1.09338080 2811178.31 1.09382271 825 3 1 1489 2813589.10 1.09423737 2815851.09 1.09462643 2817973.36 1.09499146 825 3 1 1490 2819964.44 1.09533393 2821832.35 1.09565521 2824406.41 1.09609795 825 3 1 1491 2826770.31 1.09650455 2828894.80 1.09686996 2830845.55 1.09720549 825 3 1 1492 2833232.80 1.09761611 2835323.29 1.09797567 2838008.35 1.09843751 825 3 1 1493 2840159.37 1.09880749 2841960.94 1.09911736 2843968.58 1.09946268 825 3 1 1494 2846121.19 1.09983293 2848706.48 1.10027761 2850000.00 1.10050010 825 3 1 1495 2852300.15 1.10148917 2854506.71 1.10243800 2857329.02 1.10365160 825 3 1 1496 2859977.46 1.10479044 2860000.00 1.10480013 2862462.61 1.10659784 825 3 1 1497 2864794.40 1.10830006 2866982.18 1.10989715 2870000.00 1.11210017 825 3 1 1498 2870028.43 1.11215305 2872766.76 1.11724635 2875281.63 1.12192403 825 3 1 1499 2876820.34 1.12478603 2879707.64 1.13015643 2880000.00 1.13070022 825 3 1 1500 2882000.00 1.14000023 2882236.40 1.14195054 2884000.00 1.15650025 825 3 1 1501 2884450.88 1.16522478 2886000.00 1.19520026 2887000.00 1.24420027 825 3 1 1502 2887238.71 1.27943387 2888000.00 1.39180028 2888200.00 1.46290028 825 3 1 1503 2888400.00 1.57430028 2888500.00 1.65580028 2888600.00 1.76530028 825 3 1 1504 2888700.00 1.91620028 2888800.00 2.12790028 2888900.00 2.42060028 825 3 1 1505 2889000.00 2.77480028 2889100.00 3.00100029 2889200.00 2.73750029 825 3 1 1506 2889300.00 2.09530029 2889400.00 1.56320029 2889500.00 1.26090029 825 3 1 1507 2889574.07 1.14690656 2889600.00 1.10700029 2889700.00 1.03020029 825 3 1 1508 2889800.00 .992149991 2890000.00 .966559993 2890500.00 .977239997 825 3 1 1509 2891000.00 .998510002 2892000.00 1.02830031 2892177.03 1.03087610 825 3 1 1510 2894000.00 1.05740033 2894130.79 1.05832240 2896000.00 1.07150035 825 3 1 1511 2897063.91 1.07602198 2898000.00 1.08000037 2900000.00 1.08580039 825 3 1 1512 2903100.02 1.08897478 2906009.30 1.09195386 2908739.40 1.09474946 825 3 1 1513 2911301.20 1.09737273 2913704.93 1.09983413 2917018.00 1.10322670 825 3 1 1514 2920061.24 1.10634297 2922796.81 1.10914419 2925309.10 1.11171677 825 3 1 1515 2928384.12 1.11486560 2931077.42 1.11762355 2933436.09 1.12003883 825 3 1 1516 2936465.83 1.12314131 2939632.32 1.12638382 2942220.82 1.12903447 825 3 1 1517 2944996.74 1.13187705 2947497.31 1.13443767 2950000.00 1.13700047 825 3 1 1518 2953100.44 1.14130995 2956010.06 1.14535421 2958740.43 1.14914932 825 3 1 1519 2962504.16 1.15438078 2965961.78 1.15918676 2969070.22 1.16350742 825 3 1 1520 2971925.24 1.16747583 2975420.17 1.17233373 2978481.60 1.17658908 825 3 1 1521 2982336.78 1.18194775 2985567.24 1.18643810 2986055.74 1.18711711 825 3 1 1522 2989168.91 1.19144444 2992887.68 1.19661359 2995425.85 1.20014171 825 3 1 1523 2998474.51 1.20437943 3000000.00 1.20649992 3001550.02 1.21366089 825 3 1 1524 3004555.47 1.22754584 3005000.00 1.22959954 3005500.00 1.23709960 825 3 1 1525 3006000.00 1.25099967 3006200.00 1.26089969 3006400.00 1.27679972 825 3 1 1526 3006500.00 1.28889973 3006600.00 1.30629975 3006700.00 1.33329976 825 3 1 1527 3006800.00 1.38039977 3006900.00 1.47969979 3007000.00 1.78259980 825 3 1 1528 3007100.00 3.06389981 3007200.00 1.31249983 3007300.00 1.12839984 825 3 1 1529 3007375.81 1.12809661 3007400.00 1.12799985 3007600.00 1.14999988 825 3 1 1530 3007800.00 1.16509991 3008000.00 1.17499994 3008400.00 1.18700000 825 3 1 1531 3009000.00 1.19670008 3010000.00 1.20540023 3011303.67 1.21017159 825 3 1 1532 3014835.31 1.22309724 3015000.00 1.22370000 3018079.42 1.23148455 825 3 1 1533 3021926.96 1.24121092 3025421.91 1.25004601 3028483.31 1.25778516 825 3 1 1534 3032416.64 1.26772859 3034609.00 1.27327090 3038449.45 1.28297967 825 3 1 1535 3040000.00 1.28689955 3042415.01 1.29397551 3045121.77 1.30190637 825 3 1 1536 3048373.06 1.31143278 3050000.00 1.31619981 3053101.24 1.32637201 825 3 1 1537 3057376.66 1.34039568 3060000.00 1.34900050 3061304.85 1.35408270 825 3 1 1538 3064836.72 1.36783892 3068080.98 1.38047504 3072052.82 1.39594516 825 3 1 1539 3075532.39 1.40949806 3080000.00 1.42689956 3080003.62 1.42691716 825 3 1 1540 3083587.19 1.44433290 3086589.69 1.45892485 3089936.82 1.47519182 825 3 1 1541 3093527.05 1.49264045 3097840.85 1.51360593 3100000.00 1.52409972 825 3 1 1542 3102492.97 1.53905717 3106860.50 1.56526195 3111370.95 1.59232463 825 3 1 1543 3114450.01 1.61079922 3118148.91 1.63299317 3120000.00 1.64410012 825 3 1 1544 3122493.02 1.66224873 3126860.59 1.69404401 3131371.05 1.72688004 825 3 1 1545 3136298.97 1.76275582 3140000.00 1.78970025 3142493.06 1.81122696 825 3 1 1546 3146860.68 1.84894042 3151547.01 1.88940661 3155770.67 1.92587837 825 3 1 1547 3160000.00 1.96239982 3164996.05 2.01036152 3170000.00 2.05840019 825 3 1 1548 3174996.06 2.10935905 3180000.00 2.16039965 3184371.14 2.20743236 825 3 1 1549 3188122.61 2.24779865 3190000.00 2.26800001 3192497.07 2.29787039 825 3 1 1550 3194371.15 2.32028926 3197184.34 2.35394367 3200000.00 2.38762938 825 3 1 1551 3201000.00 2.39959990 3202000.00 2.41535961 3203000.00 2.43112516 825 3 1 1552 3204000.00 2.44689982 3205000.00 2.46719992 3206000.00 2.49259983 825 3 1 1553 3207000.00 2.52739995 3208000.00 2.58240000 3209000.00 2.68750042 825 3 1 1554 3210000.00 2.95489952 3210500.00 3.27740022 3211000.00 3.93590032 825 3 1 1555 3211100.00 4.12789982 3211200.00 4.33879992 3211300.00 4.56166592 825 3 1 1556 3211400.00 4.78440022 3211500.00 4.98680012 3211600.00 5.14459992 825 3 1 1557 3211700.00 5.23400012 3211800.00 5.23899952 3211900.00 5.15849982 825 3 1 1558 3212000.00 5.00659962 3212200.00 4.58349972 3212400.00 4.14399992 825 3 1 1559 3212600.00 3.77610032 3212800.00 3.49459972 3213000.00 3.28589972 825 3 1 1560 3213200.00 3.13190032 3213400.00 3.01720042 3213600.00 2.93090032 825 3 1 1561 3213800.00 2.86479952 3214000.00 2.81370042 3214200.00 2.77350012 825 3 1 1562 3214400.00 2.74159972 3214600.00 2.71844322 3214800.00 2.69529952 825 3 1 1563 3215000.00 2.67840037 3216000.00 2.62939962 3217000.00 2.61050021 825 3 1 1564 3218000.00 2.60449964 3219000.00 2.60659249 3220000.00 2.60869952 825 3 1 1565 3222000.00 2.62364140 3224000.00 2.63859960 3226000.00 2.65743731 825 3 1 1566 3228000.00 2.67627972 3230000.00 2.69512501 3235000.00 2.74224536 825 3 1 1567 3240000.00 2.78937120 3245000.00 2.83650003 3250000.00 2.87746550 825 3 1 1568 3253265.99 2.90422533 3260000.00 2.95940032 3270000.00 3.02739969 825 3 1 1569 3280000.00 3.08320081 3285000.00 3.10333337 3295000.00 3.14359994 825 3 1 1570 3310000.00 3.17799879 3326000.00 3.19030010 3328000.00 3.18925838 825 3 1 1571 3345000.00 3.18039903 3350000.00 3.17292052 3370000.00 3.14299992 825 3 1 1572 3400500.00 3.08822921 3410000.00 3.07686296 3420000.00 3.06490394 825 3 1 1573 3430000.00 3.05300042 3435000.00 3.05715252 3436000.00 3.05820022 825 3 1 1574 3437000.00 3.06750665 3437500.00 3.07269992 3438000.00 3.08740012 825 3 1 1575 3438500.00 3.14320002 3439000.00 3.97820002 3439500.00 4.04300002 825 3 1 1576 3440000.00 3.60200002 3440500.00 3.72990022 3441000.00 4.22240042 825 3 1 1577 3441500.00 5.27770002 3441600.00 5.47910002 3441700.00 5.60950002 825 3 1 1578 3441800.00 5.63820002 3441900.00 5.55640002 3442000.00 5.38220002 825 3 1 1579 3442500.00 4.24170042 3443000.00 3.64220012 3443500.00 3.38529972 825 3 1 1580 3444000.00 3.26119992 3444500.00 3.19330032 3445000.00 3.15230002 825 3 1 1581 3450000.00 3.05509962 3455000.00 3.03879952 3460000.00 3.03311898 825 3 1 1582 3465000.00 3.02745605 3470000.00 3.02180022 3480000.00 3.01889495 825 3 1 1583 3500000.00 3.01310022 3520000.00 3.01929712 3530000.00 3.02240177 825 3 1 1584 3540000.00 3.02947117 3546049.38 3.03375219 3560000.00 3.04362477 825 3 1 1585 3570000.00 3.05070832 3580000.00 3.05779697 3590000.00 3.06489142 825 3 1 1586 3600000.00 3.07199217 3610000.00 3.07910012 3620000.00 3.08164532 825 3 1 1587 3630000.00 3.08419972 3640000.00 3.08245639 3642000.00 3.08211450 825 3 1 1588 3644000.00 3.08179562 3645000.00 3.08170293 3645200.00 3.08171321 825 3 1 1589 3645400.00 3.08175379 3645600.00 3.08185987 3645800.00 3.08213565 825 3 1 1590 3646000.00 3.08301523 3646200.00 3.08789992 3646400.00 3.10740002 825 3 1 1591 3646600.00 3.08489024 3646800.00 3.08230366 3647000.00 3.08154768 825 3 1 1592 3647200.00 3.08115530 3647400.00 3.08087932 3647600.00 3.08065175 825 3 1 1593 3647800.00 3.08044767 3648000.00 3.08025639 3649000.00 3.07937190 825 3 1 1594