JENDL-5 (Neutron sublibrary (activation cs)) Cf-251 0 0 0 0 9.825100+4 2.489230+2 0 0 6 19858 1451 1 0.000000+0 1.000000+0 0 0 0 69858 1451 2 1.000000+0 2.000000+7 0 0 10 59858 1451 3 2.936000+2 0.000000+0 4 0 366 149858 1451 4 98-Cf-251 JAEA+ EVAL-JAN10 O.Iwamoto,T.Nakagawa,+ 9858 1451 5 DIST-DEC21 20100318 9858 1451 6 ----JENDL-5 MATERIAL 9858 9858 1451 7 -----INCIDENT NEUTRON DATA 9858 1451 8 ------ENDF-6 FORMAT 9858 1451 9 9858 1451 10 History 9858 1451 11 06-05 Resonance parameters were evaluated. 9858 1451 12 07-09 Theoretical calculation was done with CCONE code. 9858 1451 13 Data were compiled as JENDL/AC-2008/1/. 9858 1451 14 09-08 (MF1,MT458) was evaluated. 9858 1451 15 09-12 Theoretical calculation was done with CCONE code. 9858 1451 16 10-01 Data of prompt gamma rays due to fission were given. 9858 1451 17 10-03 Covariance data were added. 9858 1451 18 9858 1451 19 21-11 revised by O.Iwamoto 9858 1451 20 (MF3/MT19-21,38) deleted 9858 1451 21 (MF8/MT16-18,37,102) JENDL/AD-2017 adopted 9858 1451 22 (MF8/MT4) added 9858 1451 23 9858 1451 24 MF= 1 General information 9858 1451 25 MT=452 Number of Neutrons per fission 9858 1451 26 Sum of MT's = 455 and 456. 9858 1451 27 9858 1451 28 MT=455 Delayed neutron data 9858 1451 29 Semi-empirical formula by Tuttle/2/. 9858 1451 30 Decay constants were evaluated by Brady and England/3/. 9858 1451 31 9858 1451 32 MT=456 Number of prompt neutrons per fission 9858 1451 33 (same as JENDL-3.3) 9858 1451 34 At the thermal energy, the data of Flynn et al./4/ was 9858 1451 35 adopted. An energy dependent term was based on the semi- 9858 1451 36 empirical formula by Howerton/5/. 9858 1451 37 9858 1451 38 MT=458 Components of energy release due to fission 9858 1451 39 Total energy and prompt energy were calculated from mass 9858 1451 40 balance using JENDL-4 fission yields data and mass excess 9858 1451 41 evaluation. Mass excess values were from Audi's 2009 9858 1451 42 evaluation/6/. Delayed energy values were calculated from 9858 1451 43 the energy release for infinite irradiation using JENDL FP 9858 1451 44 Decay Data File 2000 and JENDL-4 yields data. For delayed 9858 1451 45 neutron energy, as the JENDL FP Decay Data File 2000/7/ does 9858 1451 46 not include average neutron energy values, the average values 9858 1451 47 were calculated using the formula shown in the report by 9858 1451 48 T.R. England/8/. The fractions of prompt energy were 9858 1451 49 calculated using the fractions of Sher's evaluation/9/ when 9858 1451 50 they were provided. When the fractions were not given by Sher,9858 1451 51 averaged fractions were used. 9858 1451 52 9858 1451 53 9858 1451 54 MF= 2 Resonance parameters 9858 1451 55 MT=151 9858 1451 56 Resolved resonance parameters (MLBW: 1.0e-5 - 5.0 eV) 9858 1451 57 Measured resonance parameters were reported by Anufriev and 9858 1451 58 Sivukha/10/. Their parameters were adopted and modified 9858 1451 59 so as to reproduce thermal cross sections: 9858 1451 60 capture = 2864+-150 /11/ 9858 1451 61 fission = 4939+-228 /12,4/ 9858 1451 62 9858 1451 63 Unresolved resonance parameters (5 eV - 30 keV) 9858 1451 64 Parameters (URP) were determined with ASREP code/13/ so as to 9858 1451 65 reproduce the cross sections in this energy region. URP are 9858 1451 66 used only for self-shielding calculations. 9858 1451 67 9858 1451 68 Thermal cross sections and resonance integrals (at 300K) 9858 1451 69 ------------------------------------------------------- 9858 1451 70 0.0253 eV reson. integ.(*) 9858 1451 71 (barns) (barns) 9858 1451 72 ------------------------------------------------------- 9858 1451 73 total 7812.1 9858 1451 74 elastic 8.94 9858 1451 75 fission 4938.8 1033 9858 1451 76 capture 2864.3 519 9858 1451 77 ------------------------------------------------------- 9858 1451 78 (*) In the energy range from 0.5 eV to 10 MeV. 9858 1451 79 9858 1451 80 9858 1451 81 MF= 3 Neutron cross sections 9858 1451 82 Cross sections above the resolved resonance region were 9858 1451 83 calculated with CCONE code/14/. 9858 1451 84 9858 1451 85 MT= 1 Total cross section 9858 1451 86 The cross section was calculated with CC OMP of Soukhovitskii 9858 1451 87 et al./15/ 9858 1451 88 9858 1451 89 9858 1451 90 MF= 4 Angular distributions of secondary neutrons 9858 1451 91 MT=2 Elastic scattering 9858 1451 92 Calculated with CCONE code/14/. 9858 1451 93 9858 1451 94 MT=18 Fission 9858 1451 95 Isotropic distributions in the laboratory system were assumed.9858 1451 96 9858 1451 97 9858 1451 98 MF= 5 Energy distributions of secondary neutrons 9858 1451 99 MT=18 Prompt neutrons 9858 1451 100 Calculated with CCONE code/14/. 9858 1451 101 9858 1451 102 MT=455 Delayed neutrons 9858 1451 103 Calculated by Brady and England/3/. 9858 1451 104 9858 1451 105 9858 1451 106 MF= 6 Energy-angle distributions 9858 1451 107 Calculated with CCONE code/14/. 9858 1451 108 Distributions from fission (MT=18) are not included. 9858 1451 109 9858 1451 110 9858 1451 111 MF=12 Photon production multiplicities 9858 1451 112 MT=18 Fission 9858 1451 113 Calculated from the total energy released by the prompt 9858 1451 114 gamma-rays due to fission given in MF=1/MT=458 and the 9858 1451 115 average energy of gamma-rays. 9858 1451 116 9858 1451 117 9858 1451 118 MF=14 Photon angular distributions 9858 1451 119 MT=18 Fission 9858 1451 120 Isotoropic distributions were assumed. 9858 1451 121 9858 1451 122 9858 1451 123 MF=15 Continuous photon energy spectra 9858 1451 124 MT=18 Fission 9858 1451 125 Experimental data measured by Verbinski et al./16/ for 9858 1451 126 Pu-239 thermal fission were adopted. 9858 1451 127 9858 1451 128 9858 1451 129 MF=31 Covariances of average number of neutrons per fission 9858 1451 130 MT=452 Number of neutrons per fission 9858 1451 131 Sum of covariances for MT=455 and MT=456. 9858 1451 132 9858 1451 133 MT=455 9858 1451 134 Error of 15% was assumed. 9858 1451 135 9858 1451 136 MT=456 9858 1451 137 Covariance was obtained by fitting a linear function to the 9858 1451 138 data at 0.0 and 5.0 MeV with an uncertainty of 12% which was 9858 1451 139 estimated from the experimental data of Flynn et al./4/ 9858 1451 140 9858 1451 141 9858 1451 142 MF=32 Covariances of resonance parameters 9858 1451 143 MT=151 Resolved resonance parameterss 9858 1451 144 Format of LCOMP=0 was adopted. 9858 1451 145 9858 1451 146 Uncertainties of parameters were taken from Mughabghab /17/. 9858 1451 147 For the parameters without any information on uncertainty, 9858 1451 148 the following uncertainties were assumed: 9858 1451 149 Resonance energy 0.1 % 9858 1451 150 Neutron width 10 % 9858 1451 151 Capture width 10 % 9858 1451 152 Fission width 10 % 9858 1451 153 9858 1451 154 They were further modified by considering experimental data 9858 1451 155 of the fission and capture cross sections at the thermal 9858 1451 156 neutron energy. 9858 1451 157 9858 1451 158 9858 1451 159 MF=33 Covariances of neutron cross sections 9858 1451 160 Covariances were given to all the cross sections by using 9858 1451 161 KALMAN code/18/ and the covariances of model parameters 9858 1451 162 used in the cross-section calculations. 9858 1451 163 9858 1451 164 In the resolved resonance region, the following standard 9858 1451 165 deviations were added to the contributions from resonance 9858 1451 166 parameters: 9858 1451 167 Elastic scattering 20 % 9858 1451 168 9858 1451 169 9858 1451 170 MF=34 Covariances for Angular Distributions 9858 1451 171 MT=2 Elastic scattering 9858 1451 172 Covariances were given only to P1 components. 9858 1451 173 9858 1451 174 9858 1451 175 MF=35 Covariances for Energy Distributions 9858 1451 176 MT=18 Fission spectra 9858 1451 177 Estimated with CCONE and KALMAN codes. 9858 1451 178 9858 1451 179 9858 1451 180 ***************************************************************** 9858 1451 181 Calculation with CCONE code 9858 1451 182 ***************************************************************** 9858 1451 183 9858 1451 184 Models and parameters used in the CCONE/14/ calculation 9858 1451 185 1) Coupled channel optical model 9858 1451 186 Levels in the rotational band were included. Optical model 9858 1451 187 potential and coupled levels are shown in Table 1. 9858 1451 188 9858 1451 189 2) Two-component exciton model/19/ 9858 1451 190 * Global parametrization of Koning-Duijvestijn/20/ 9858 1451 191 was used. 9858 1451 192 * Gamma emission channel/21/ was added to simulate direct 9858 1451 193 and semi-direct capture reaction. 9858 1451 194 9858 1451 195 3) Hauser-Feshbach statistical model 9858 1451 196 * Moldauer width fluctuation correction/22/ was included. 9858 1451 197 * Neutron, gamma and fission decay channel were included. 9858 1451 198 * Transmission coefficients of neutrons were taken from 9858 1451 199 coupled channel calculation in Table 1. 9858 1451 200 * The level scheme of the target is shown in Table 2. 9858 1451 201 * Level density formula of constant temperature and Fermi-gas 9858 1451 202 model were used with shell energy correction and collective 9858 1451 203 enhancement factor. Parameters are shown in Table 3. 9858 1451 204 * Fission channel: 9858 1451 205 Double humped fission barriers were assumed. 9858 1451 206 Fission barrier penetrabilities were calculated with 9858 1451 207 Hill-Wheler formula/23/. Fission barrier parameters were 9858 1451 208 shown in Table 4. Transition state model was used and 9858 1451 209 continuum levels are assumed above the saddles. The level 9858 1451 210 density parameters for inner and outer saddles are shown in 9858 1451 211 Tables 5 and 6, respectively. 9858 1451 212 * Gamma-ray strength function of Kopecky et al/24/,/25/ 9858 1451 213 was used. The prameters are shown in Table 7. 9858 1451 214 9858 1451 215 9858 1451 216 ------------------------------------------------------------------9858 1451 217 Tables 9858 1451 218 ------------------------------------------------------------------9858 1451 219 9858 1451 220 Table 1. Coupled channel calculation 9858 1451 221 -------------------------------------------------- 9858 1451 222 * rigid rotor model was applied 9858 1451 223 * coupled levels = 0,1,2,3,5,9,12 (see Table 2) 9858 1451 224 * optical potential parameters /15/ 9858 1451 225 Volume: 9858 1451 226 V_0 = 49.97 MeV 9858 1451 227 lambda_HF = 0.01004 1/MeV 9858 1451 228 C_viso = 15.9 MeV 9858 1451 229 A_v = 12.04 MeV 9858 1451 230 B_v = 81.36 MeV 9858 1451 231 E_a = 385 MeV 9858 1451 232 r_v = 1.2568 fm 9858 1451 233 a_v = 0.633 fm 9858 1451 234 Surface: 9858 1451 235 W_0 = 17.2 MeV 9858 1451 236 B_s = 11.19 MeV 9858 1451 237 C_s = 0.01361 1/MeV 9858 1451 238 C_wiso = 23.5 MeV 9858 1451 239 r_s = 1.1803 fm 9858 1451 240 a_s = 0.601 fm 9858 1451 241 Spin-orbit: 9858 1451 242 V_so = 5.75 MeV 9858 1451 243 lambda_so = 0.005 1/MeV 9858 1451 244 W_so = -3.1 MeV 9858 1451 245 B_so = 160 MeV 9858 1451 246 r_so = 1.1214 fm 9858 1451 247 a_so = 0.59 fm 9858 1451 248 Coulomb: 9858 1451 249 C_coul = 1.3 9858 1451 250 r_c = 1.2452 fm 9858 1451 251 a_c = 0.545 fm 9858 1451 252 Deformation: 9858 1451 253 beta_2 = 0.213 9858 1451 254 beta_4 = 0.066 9858 1451 255 beta_6 = 0.0015 9858 1451 256 9858 1451 257 * Calculated strength function 9858 1451 258 S0= 1.53e-4 S1= 2.25e-4 R'= 9.32 fm (En=1 keV) 9858 1451 259 -------------------------------------------------- 9858 1451 260 9858 1451 261 Table 2. Level Scheme of Cf-251 9858 1451 262 ------------------- 9858 1451 263 No. Ex(MeV) J PI 9858 1451 264 ------------------- 9858 1451 265 0 0.00000 1/2 + * 9858 1451 266 1 0.02482 3/2 + * 9858 1451 267 2 0.04783 5/2 + * 9858 1451 268 3 0.10573 7/2 + * 9858 1451 269 4 0.10630 7/2 + 9858 1451 270 5 0.14646 9/2 + * 9858 1451 271 6 0.16631 9/2 + 9858 1451 272 7 0.17769 3/2 + 9858 1451 273 8 0.21172 5/2 + 9858 1451 274 9 0.23776 11/2 + * 9858 1451 275 10 0.23934 11/2 + 9858 1451 276 11 0.25844 7/2 + 9858 1451 277 12 0.29570 13/2 + * 9858 1451 278 13 0.31929 9/2 + 9858 1451 279 14 0.32535 13/2 + 9858 1451 280 ------------------- 9858 1451 281 *) Coupled levels in CC calculation 9858 1451 282 9858 1451 283 Table 3. Level density parameters 9858 1451 284 -------------------------------------------------------- 9858 1451 285 Nuclide a* Pair Eshell T E0 Ematch 9858 1451 286 1/MeV MeV MeV MeV MeV MeV 9858 1451 287 -------------------------------------------------------- 9858 1451 288 Cf-252 20.8380 1.5119 1.7395 0.3684 -0.1685 3.7959 9858 1451 289 Cf-251 19.2285 0.7574 1.2773 0.3926 -0.9361 3.0632 9858 1451 290 Cf-250 19.1626 1.5179 1.0208 0.3974 -0.1838 3.8400 9858 1451 291 Cf-249 19.0966 0.7605 0.7689 0.3773 -0.6847 2.7641 9858 1451 292 Cf-248 19.0305 1.5240 0.7495 0.3921 -0.0631 3.7096 9858 1451 293 -------------------------------------------------------- 9858 1451 294 9858 1451 295 Table 4. Fission barrier parameters 9858 1451 296 ---------------------------------------- 9858 1451 297 Nuclide V_A hw_A V_B hw_B 9858 1451 298 MeV MeV MeV MeV 9858 1451 299 ---------------------------------------- 9858 1451 300 Cf-252 6.000 1.040 5.000 0.800 9858 1451 301 Cf-251 6.200 0.800 5.000 0.600 9858 1451 302 Cf-250 6.200 1.040 5.400 0.600 9858 1451 303 Cf-249 6.700 1.200 5.900 0.800 9858 1451 304 Cf-248 6.200 1.040 5.400 0.600 9858 1451 305 ---------------------------------------- 9858 1451 306 9858 1451 307 Table 5. Level density above inner saddle 9858 1451 308 -------------------------------------------------------- 9858 1451 309 Nuclide a* Pair Eshell T E0 Ematch 9858 1451 310 1/MeV MeV MeV MeV MeV MeV 9858 1451 311 -------------------------------------------------------- 9858 1451 312 Cf-252 21.6098 1.7638 2.5000 0.3202 -0.6492 3.7638 9858 1451 313 Cf-251 21.5360 0.8837 2.5000 0.3208 -1.5294 2.8837 9858 1451 314 Cf-250 21.4621 1.7709 2.5000 0.2827 -0.1068 3.2709 9858 1451 315 Cf-249 20.0514 0.8872 2.5000 0.3486 -1.7837 3.0872 9858 1451 316 Cf-248 21.3142 1.7780 2.5000 0.3226 -0.6352 3.7780 9858 1451 317 -------------------------------------------------------- 9858 1451 318 9858 1451 319 Table 6. Level density above outer saddle 9858 1451 320 -------------------------------------------------------- 9858 1451 321 Nuclide a* Pair Eshell T E0 Ematch 9858 1451 322 1/MeV MeV MeV MeV MeV MeV 9858 1451 323 -------------------------------------------------------- 9858 1451 324 Cf-252 21.6098 1.7638 1.0400 0.3477 0.0528 3.7638 9858 1451 325 Cf-251 21.5360 0.8837 1.0000 0.3488 -0.8268 2.8837 9858 1451 326 Cf-250 21.4621 1.7709 0.9600 0.3499 0.0610 3.7709 9858 1451 327 Cf-249 20.0514 0.8872 0.9200 0.3794 -1.0059 3.0872 9858 1451 328 Cf-248 21.3142 1.7780 0.8800 0.3522 0.0693 3.7780 9858 1451 329 -------------------------------------------------------- 9858 1451 330 9858 1451 331 Table 7. Gamma-ray strength function for Cf-252 9858 1451 332 -------------------------------------------------------- 9858 1451 333 K0 = 2.200 E0 = 4.500 (MeV) 9858 1451 334 * E1: ER = 11.35 (MeV) EG = 2.69 (MeV) SIG = 257.38 (mb) 9858 1451 335 ER = 14.25 (MeV) EG = 4.16 (MeV) SIG = 514.75 (mb) 9858 1451 336 * M1: ER = 6.49 (MeV) EG = 4.00 (MeV) SIG = 2.49 (mb) 9858 1451 337 * E2: ER = 9.97 (MeV) EG = 3.09 (MeV) SIG = 7.35 (mb) 9858 1451 338 -------------------------------------------------------- 9858 1451 339 9858 1451 340 9858 1451 341 References 9858 1451 342 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9858 1451 343 2) R.J.Tuttle: INDC(NDS)-107/G+Special, p.29 (1979). 9858 1451 344 3) M.C.Brady, T.R.England: Nucl. Sci. Eng., 103, 129 (1989). 9858 1451 345 4) K.F.Flynn et al.: Phys. Rev., C11, 1676 (1975). 9858 1451 346 5) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9858 1451 347 6) G.Audi: Private communication (April 2009). 9858 1451 348 7) J.Katakura et al.: JAERI 1343 (2001). 9858 1451 349 8) T.R.England et al.: LA-11151-MS (1988). 9858 1451 350 9) R.Sher, C.Beck: EPRI NP-1771 (1981). 9858 1451 351 10) V.A.Anufriev, V.I.Sivukha: Sov. At. Energy, 74, 69 (1993). 9858 1451 352 11) J.Halperin et al.: ORNL-4706, p.47 (1971). 9858 1451 353 12) R.C.Ragani et al.: Phys. Rev., C9, 399 (1974). 9858 1451 354 13) Y.Kikuchi et al.: JAERI-Data/Code 99-025 (1999) in Japanese. 9858 1451 355 14) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9858 1451 356 15) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9858 1451 357 16) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9858 1451 358 17) S.F.Mughabghab: "Atlas of Neutron Resonances," Elsevier 9858 1451 359 (2006). 9858 1451 360 18) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9858 1451 361 Japanese. 9858 1451 362 19) C.Kalbach: Phys. Rev. C33, 818 (1986). 9858 1451 363 20) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9858 1451 364 21) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9858 1451 365 22) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9858 1451 366 23) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9858 1451 367 24) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9858 1451 368 25) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9858 1451 369 9858 1451 370 1 451 384 19858 1451 371 2 151 4 19858 1451 372 3 4 31 19858 1451 373 3 16 14 19858 1451 374 3 17 9 19858 1451 375 3 18 207 19858 1451 376 3 37 5 19858 1451 377 3 102 233 19858 1451 378 8 4 2 19858 1451 379 8 16 2 19858 1451 380 8 17 2 19858 1451 381 8 18 2 19858 1451 382 8 37 2 19858 1451 383 8 102 2 19858 1451 384 9858 1 099999 9858 0 0 0 9.825100+4 2.489230+2 0 0 1 09858 2151 1 9.825100+4 1.000000+0 0 0 1 09858 2151 2 1.000000-5 5.000000+0 0 0 0 09858 2151 3 5.000000-1 9.250000-1 0 0 0 09858 2151 4 9858 2 099999 9858 0 0 0 9.825100+4 2.489230+2 0 0 0 09858 3 4 1 0.000000+0-2.482500+4 0 0 1 829858 3 4 2 82 2 9858 3 4 3 2.492470+4 0.000000+0 3.000000+4 2.319620-1 4.802010+4 3.578380-19858 3 4 4 5.000000+4 3.714249-1 7.000000+4 5.042345-1 1.000000+5 6.930420-19858 3 4 5 1.030770+5 7.084860-1 1.061550+5 7.239391-1 1.067310+5 7.280233-19858 3 4 6 1.200000+5 8.071288-1 1.400000+5 9.130761-1 1.470480+5 9.489401-19858 3 4 7 1.669780+5 1.045718+0 1.700000+5 1.060205+0 1.784040+5 1.100321+09858 3 4 8 2.000000+5 1.282570+0 2.125700+5 1.342484+0 2.125710+5 1.342487+09858 3 4 9 2.387150+5 1.477495+0 2.403020+5 1.484829+0 2.500000+5 1.528495+09858 3 4 10 2.594780+5 1.568613+0 2.968880+5 1.726936+0 3.000000+5 1.739325+09858 3 4 11 3.205730+5 1.773330+0 3.266570+5 1.782426+0 4.000000+5 1.873105+09858 3 4 12 5.000000+5 2.033609+0 6.000000+5 2.099851+0 7.000000+5 2.205637+09858 3 4 13 8.000000+5 2.280340+0 9.000000+5 2.360966+0 1.000000+6 2.447715+09858 3 4 14 1.100000+6 2.529283+0 1.200000+6 2.604384+0 1.300000+6 2.664293+09858 3 4 15 1.400000+6 2.714852+0 1.500000+6 2.740129+0 1.600000+6 2.757681+09858 3 4 16 1.700000+6 2.748749+0 1.800000+6 2.734241+0 1.900000+6 2.700377+09858 3 4 17 2.000000+6 2.662892+0 2.100000+6 2.614479+0 2.300000+6 2.511856+09858 3 4 18 2.500000+6 2.405809+0 2.700000+6 2.305524+0 3.000000+6 2.171405+09858 3 4 19 3.500000+6 2.029342+0 4.000000+6 1.930273+0 4.500000+6 1.890386+09858 3 4 20 5.000000+6 1.867531+0 5.500000+6 1.751637+0 6.000000+6 1.401716+09858 3 4 21 6.500000+6 1.111261+0 7.000000+6 9.136658-1 7.500000+6 7.790624-19858 3 4 22 8.000000+6 6.966005-1 8.500000+6 6.378381-1 9.000000+6 5.968569-19858 3 4 23 9.500000+6 5.634210-1 1.000000+7 5.359447-1 1.050000+7 5.117560-19858 3 4 24 1.100000+7 4.903665-1 1.150000+7 4.707763-1 1.200000+7 4.515186-19858 3 4 25 1.250000+7 4.334295-1 1.300000+7 4.162742-1 1.350000+7 4.003073-19858 3 4 26 1.400000+7 3.855658-1 1.450000+7 3.715593-1 1.500000+7 3.575859-19858 3 4 27 1.550000+7 3.459483-1 1.600000+7 3.343474-1 1.650000+7 3.238172-19858 3 4 28 1.700000+7 3.132810-1 1.750000+7 3.037258-1 1.800000+7 2.948084-19858 3 4 29 1.850000+7 2.863482-1 1.900000+7 2.783595-1 1.950000+7 2.714491-19858 3 4 30 2.000000+7 2.641351-1 9858 3 4 31 9858 3 099999 9.825100+4 2.489230+2 0 0 0 09858 3 16 1 -5.108490+6-5.108490+6 0 0 1 319858 3 16 2 31 2 9858 3 16 3 5.129020+6 0.000000+0 5.500000+6 1.023070-1 6.000000+6 4.379340-19858 3 16 4 6.500000+6 6.183000-1 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