JENDL-5 (Neutron sublibrary (activation cs)) Pu-237 0 0 0 0 9.423700+4 2.350120+2 0 0 6 19431 1451 1 0.000000+0 1.000000+0 0 0 0 69431 1451 2 1.000000+0 2.000000+7 0 0 10 59431 1451 3 2.936000+2 0.000000+0 4 0 343 129431 1451 4 94-Pu-237 JAEA+ EVAL-FEB10 O.Iwamoto,T.Nakagawa+ 9431 1451 5 DIST-DEC21 20100303 9431 1451 6 ----JENDL-5 MATERIAL 9431 9431 1451 7 -----INCIDENT NEUTRON DATA 9431 1451 8 ------ENDF-6 FORMAT 9431 1451 9 9431 1451 10 History 9431 1451 11 07-05 Theoretical calculation was made with CCONE code. 9431 1451 12 07-10 Theoretical calculation was made with CCONE code. 9431 1451 13 Data were compiled as JENDL/AC-2008/1/. 9431 1451 14 10-02 Data of prompt gamma rays due to fission were given. 9431 1451 15 10-03 Covariance data were given. 9431 1451 16 9431 1451 17 21-11 revised by O.Iwamoto 9431 1451 18 (MF3/MT19-21,38) deleted 9431 1451 19 (MF8/MT4,16-18,102) added 9431 1451 20 9431 1451 21 MF= 1 General information 9431 1451 22 MT=452 Number of Neutrons per fission 9431 1451 23 Sum of MT's = 455 and 456. 9431 1451 24 9431 1451 25 MT=455 Delayed neutron data 9431 1451 26 (same as JENDL-3.3) 9431 1451 27 Determined from the systematics of Manero and Konshin /2/. 9431 1451 28 9431 1451 29 MT=456 Number of prompt neutrons per fission 9431 1451 30 (same as JENDL-3.3) 9431 1451 31 Determined from the data for Pu-239. 9431 1451 32 9431 1451 33 MF= 2 Resonance parameters 9431 1451 34 MT=151 9431 1451 35 No resolved resonance parameters 9431 1451 36 9431 1451 37 9431 1451 38 Thermal cross sections and resonance integrals (at 300K) 9431 1451 39 ------------------------------------------------------- 9431 1451 40 0.0253 eV reson. integ.(*) 9431 1451 41 (barns) (barns) 9431 1451 42 ------------------------------------------------------- 9431 1451 43 total 2507.1 9431 1451 44 elastic 11.12 9431 1451 45 fission 2295.6 1230 9431 1451 46 capture 200.1 113 9431 1451 47 ------------------------------------------------------- 9431 1451 48 (*) In the energy range from 0.5 eV to 10 MeV. 9431 1451 49 9431 1451 50 9431 1451 51 MF= 3 Neutron cross sections 9431 1451 52 In the energy region below 0.3 eV: 9431 1451 53 Elastic scattering = 11.1 b which was estimated from R=9.397 9431 1451 54 fm calculated with CCONE code/3/. 9431 1451 55 Fission = 1/v shape with 2294 b /4,5/ at 9431 1451 56 0.0253 eV. 9431 1451 57 Capture = 1/v shape with 200 b at 0.0253 eV. The 9431 1451 58 thermal cross section was assumed from 9431 1451 59 capture to fission ratio at 1 eV and 9431 1451 60 thermal fission cross section. 9431 1451 61 Total = sum of these three cross sections. 9431 1451 62 9431 1451 63 Above 0.3 eV: 9431 1451 64 All the cross sections were calculated with CCONE code/3/. 9431 1451 65 9431 1451 66 MT= 1 Total cross section 9431 1451 67 The cross section was calculated with CC OMP of Soukhovitskii 9431 1451 68 et al./6/. 9431 1451 69 9431 1451 70 MT=18 Fission cross section 9431 1451 71 The simulated (n,f) cross sections of Britt and Wilhelmy/7/ 9431 1451 72 were used to determine the parameters in the CCONE 9431 1451 73 calculation. 9431 1451 74 9431 1451 75 9431 1451 76 MF= 4 Angular distributions of secondary neutrons 9431 1451 77 MT=2 Elastic scattering 9431 1451 78 Calculated with CCONE code. 9431 1451 79 9431 1451 80 MT=18 Fission 9431 1451 81 Isotropic distributions in the laboratory system were assumed.9431 1451 82 9431 1451 83 9431 1451 84 MF= 5 Energy distributions of secondary neutrons 9431 1451 85 MT=18 Prompt fission neutrons 9431 1451 86 Calculated with CCONE code. 9431 1451 87 9431 1451 88 9431 1451 89 MF= 6 Energy-angle distributions 9431 1451 90 Calculated with CCONE code. 9431 1451 91 Distributions from fission (MT=18) are not included. 9431 1451 92 9431 1451 93 9431 1451 94 MF=12 Photon production multiplicities 9431 1451 95 MT=18 Fission 9431 1451 96 Calculated from the total energy released by the prompt 9431 1451 97 gamma-rays due to fission which was estimated from its 9431 1451 98 systematics, and the average energy of gamma-rays. 9431 1451 99 9431 1451 100 9431 1451 101 MF=14 Photon angular distributions 9431 1451 102 MT=18 Fission 9431 1451 103 Isotoropic distributions were assumed. 9431 1451 104 9431 1451 105 9431 1451 106 MF=15 Continuous photon energy spectra 9431 1451 107 MT=18 Fission 9431 1451 108 Experimental data measured by Verbinski et al./8/ for 9431 1451 109 Pu-239 thermal fission were adopted. 9431 1451 110 9431 1451 111 9431 1451 112 MF=31 Covariances of average number of neutrons per fission 9431 1451 113 MT=452 Number of neutrons per fission 9431 1451 114 Sum of covariances for MT=455 and MT=456. 9431 1451 115 9431 1451 116 MT=455 9431 1451 117 Error of 15% was assumed. 9431 1451 118 9431 1451 119 MT=456 9431 1451 120 Covariance was obtained by fitting a linear function to the 9431 1451 121 at 0.0 and 5.0 MeV with an uncertainty of 5%. 9431 1451 122 9431 1451 123 9431 1451 124 MF=33 Covariances of neutron cross sections 9431 1451 125 Covariances were given to all the cross sections by using 9431 1451 126 KALMAN code/9/ and the covariances of model parameters 9431 1451 127 used in the cross-section calculations. 9431 1451 128 9431 1451 129 Covariances of the fission cross section were determined from 9431 1451 130 experimental data. 9431 1451 131 9431 1451 132 For the following cross sections, standard deviations in the 9431 1451 133 energy region below 0.3 eV were assumed as follows: 9431 1451 134 9431 1451 135 Total 25 % 9431 1451 136 Elastic scattering 50 % 9431 1451 137 Fission 27 % estimated from experimental data 9431 1451 138 Capture 50 % 9431 1451 139 9431 1451 140 9431 1451 141 MF=34 Covariances for Angular Distributions 9431 1451 142 MT=2 Elastic scattering 9431 1451 143 Covariances were given only to P1 components. 9431 1451 144 9431 1451 145 9431 1451 146 MF=35 Covariances for Energy Distributions 9431 1451 147 MT=18 Fission spectra 9431 1451 148 Estimated with CCONE and KALMAN codes. 9431 1451 149 9431 1451 150 9431 1451 151 ***************************************************************** 9431 1451 152 Calculation with CCONE code 9431 1451 153 ***************************************************************** 9431 1451 154 9431 1451 155 Models and parameters used in the CCONE/3/ calculation 9431 1451 156 1) Coupled channel optical model 9431 1451 157 Levels in the rotational band were included. Optical model 9431 1451 158 potential and coupled levels are shown in Table 1. 9431 1451 159 9431 1451 160 2) Two-component exciton model/10/ 9431 1451 161 * Global parametrization of Koning-Duijvestijn/11/ 9431 1451 162 was used. 9431 1451 163 * Gamma emission channel/12/ was added to simulate direct 9431 1451 164 and semi-direct capture reaction. 9431 1451 165 9431 1451 166 3) Hauser-Feshbach statistical model 9431 1451 167 * Moldauer width fluctuation correction/13/ was included. 9431 1451 168 * Neutron, gamma and fission decay channel were included. 9431 1451 169 * Transmission coefficients of neutrons were taken from 9431 1451 170 coupled channel calculation in Table 1. 9431 1451 171 * The level scheme of the target is shown in Table 2. 9431 1451 172 * Level density formula of constant temperature and Fermi-gas 9431 1451 173 model were used with shell energy correction and collective 9431 1451 174 enhancement factor. Parameters are shown in Table 3. 9431 1451 175 * Fission channel: 9431 1451 176 Double humped fission barriers were assumed. 9431 1451 177 Fission barrier penetrabilities were calculated with 9431 1451 178 Hill-Wheler formula/14/. Fission barrier parameters were 9431 1451 179 shown in Table 4. Transition state model was used and 9431 1451 180 continuum levels are assumed above the saddles. The level 9431 1451 181 density parameters for inner and outer saddles are shown in 9431 1451 182 Tables 5 and 6, respectively. 9431 1451 183 * Gamma-ray strength function of Kopecky et al/15/,/16/ 9431 1451 184 was used. The prameters are shown in Table 7. 9431 1451 185 9431 1451 186 9431 1451 187 ------------------------------------------------------------------9431 1451 188 Tables 9431 1451 189 ------------------------------------------------------------------9431 1451 190 9431 1451 191 Table 1. Coupled channel calculation 9431 1451 192 -------------------------------------------------- 9431 1451 193 * rigid rotor model was applied 9431 1451 194 * coupled levels = 0,1,2,5,8 (see Table 2) 9431 1451 195 * optical potential parameters /6/ 9431 1451 196 Volume: 9431 1451 197 V_0 = 49.97 MeV 9431 1451 198 lambda_HF = 0.01004 1/MeV 9431 1451 199 C_viso = 15.9 MeV 9431 1451 200 A_v = 12.04 MeV 9431 1451 201 B_v = 81.36 MeV 9431 1451 202 E_a = 385 MeV 9431 1451 203 r_v = 1.2568 fm 9431 1451 204 a_v = 0.633 fm 9431 1451 205 Surface: 9431 1451 206 W_0 = 17.2 MeV 9431 1451 207 B_s = 11.19 MeV 9431 1451 208 C_s = 0.01361 1/MeV 9431 1451 209 C_wiso = 23.5 MeV 9431 1451 210 r_s = 1.1803 fm 9431 1451 211 a_s = 0.601 fm 9431 1451 212 Spin-orbit: 9431 1451 213 V_so = 5.75 MeV 9431 1451 214 lambda_so = 0.005 1/MeV 9431 1451 215 W_so = -3.1 MeV 9431 1451 216 B_so = 160 MeV 9431 1451 217 r_so = 1.1214 fm 9431 1451 218 a_so = 0.59 fm 9431 1451 219 Coulomb: 9431 1451 220 C_coul = 1.3 9431 1451 221 r_c = 1.2452 fm 9431 1451 222 a_c = 0.545 fm 9431 1451 223 Deformation: 9431 1451 224 beta_2 = 0.21978 9431 1451 225 beta_4 = 0.07667 9431 1451 226 beta_6 = -0.00869 9431 1451 227 9431 1451 228 * Calculated strength function 9431 1451 229 S0= 1.13e-4 S1= 2.86e-4 R'= 9.40 fm (En=1 keV) 9431 1451 230 -------------------------------------------------- 9431 1451 231 9431 1451 232 Table 2. Level Scheme of Pu-237 9431 1451 233 ------------------- 9431 1451 234 No. Ex(MeV) J PI 9431 1451 235 ------------------- 9431 1451 236 0 0.00000 7/2 - * 9431 1451 237 1 0.04771 9/2 - * 9431 1451 238 2 0.10600 11/2 - * 9431 1451 239 3 0.14554 1/2 + 9431 1451 240 4 0.15545 3/2 + 9431 1451 241 5 0.17500 13/2 - * 9431 1451 242 6 0.20118 5/2 + 9431 1451 243 7 0.22425 7/2 + 9431 1451 244 8 0.25700 15/2 - * 9431 1451 245 9 0.28022 5/2 + 9431 1451 246 10 0.30400 9/2 + 9431 1451 247 11 0.32097 7/2 + 9431 1451 248 12 0.37040 3/2 + 9431 1451 249 13 0.37100 9/2 + 9431 1451 250 14 0.40419 5/2 + 9431 1451 251 15 0.40783 5/2 + 9431 1451 252 16 0.43841 7/2 + 9431 1451 253 17 0.45320 7/2 + 9431 1451 254 18 0.47350 7/2 + 9431 1451 255 19 0.48600 9/2 + 9431 1451 256 20 0.51300 9/2 + 9431 1451 257 21 0.54500 1/2 - 9431 1451 258 22 0.58200 5/2 - 9431 1451 259 23 0.59100 3/2 - 9431 1451 260 24 0.65500 7/2 + 9431 1451 261 25 0.65530 5/2 - 9431 1451 262 26 0.69100 7/2 - 9431 1451 263 27 0.69620 7/2 - 9431 1451 264 28 0.71600 13/2 - 9431 1451 265 29 0.74100 11/2 - 9431 1451 266 30 0.75700 21/2 + 9431 1451 267 ------------------- 9431 1451 268 *) Coupled levels in CC calculation 9431 1451 269 9431 1451 270 Table 3. Level density parameters 9431 1451 271 -------------------------------------------------------- 9431 1451 272 Nuclide a* Pair Eshell T E0 Ematch 9431 1451 273 1/MeV MeV MeV MeV MeV MeV 9431 1451 274 -------------------------------------------------------- 9431 1451 275 Pu-238 18.3685 1.5557 1.9652 0.3804 0.0287 3.6608 9431 1451 276 Pu-237 18.3022 0.7795 1.8799 0.3586 -0.5090 2.5865 9431 1451 277 Pu-236 18.2358 1.5623 1.9752 0.3737 0.1216 3.5619 9431 1451 278 Pu-235 18.1694 0.7828 1.9791 0.3502 -0.4208 2.4828 9431 1451 279 Pu-234 18.1029 1.5689 2.1707 0.3732 0.1282 3.5689 9431 1451 280 -------------------------------------------------------- 9431 1451 281 9431 1451 282 Table 4. Fission barrier parameters 9431 1451 283 ---------------------------------------- 9431 1451 284 Nuclide V_A hw_A V_B hw_B 9431 1451 285 MeV MeV MeV MeV 9431 1451 286 ---------------------------------------- 9431 1451 287 Pu-238 5.300 1.040 5.850 0.600 9431 1451 288 Pu-237 5.800 0.800 5.800 0.520 9431 1451 289 Pu-236 6.000 1.040 5.000 0.600 9431 1451 290 Pu-235 6.000 0.800 5.000 0.520 9431 1451 291 Pu-234 5.600 1.040 4.600 0.600 9431 1451 292 ---------------------------------------- 9431 1451 293 9431 1451 294 Table 5. Level density above inner saddle 9431 1451 295 -------------------------------------------------------- 9431 1451 296 Nuclide a* Pair Eshell T E0 Ematch 9431 1451 297 1/MeV MeV MeV MeV MeV MeV 9431 1451 298 -------------------------------------------------------- 9431 1451 299 Pu-238 22.9607 1.8150 2.6000 0.3084 -0.5296 3.8150 9431 1451 300 Pu-237 20.1324 0.9094 2.6000 0.3320 -1.5137 2.9094 9431 1451 301 Pu-236 20.0594 1.8226 2.6000 0.3326 -0.6004 3.8226 9431 1451 302 Pu-235 19.9863 0.9133 2.6000 0.3333 -1.5098 2.9133 9431 1451 303 Pu-234 19.9132 1.8304 2.6000 0.3339 -0.5927 3.8304 9431 1451 304 -------------------------------------------------------- 9431 1451 305 9431 1451 306 Table 6. Level density above outer saddle 9431 1451 307 -------------------------------------------------------- 9431 1451 308 Nuclide a* Pair Eshell T E0 Ematch 9431 1451 309 1/MeV MeV MeV MeV MeV MeV 9431 1451 310 -------------------------------------------------------- 9431 1451 311 Pu-238 23.8791 1.8150 0.3400 0.3865 -0.5375 4.6150 9431 1451 312 Pu-237 20.1324 0.9094 0.3000 0.3706 -0.7963 2.9094 9431 1451 313 Pu-236 20.0594 1.8226 0.2600 0.3719 0.1175 3.8226 9431 1451 314 Pu-235 19.9863 0.9133 0.2200 0.3732 -0.7913 2.9133 9431 1451 315 Pu-234 19.9132 1.8304 0.1800 0.3744 0.1264 3.8304 9431 1451 316 -------------------------------------------------------- 9431 1451 317 9431 1451 318 Table 7. Gamma-ray strength function for Pu-238 9431 1451 319 -------------------------------------------------------- 9431 1451 320 K0 = 2.000 E0 = 4.500 (MeV) 9431 1451 321 * E1: ER = 10.90 (MeV) EG = 2.50 (MeV) SIG = 300.00 (mb) 9431 1451 322 ER = 13.80 (MeV) EG = 4.70 (MeV) SIG = 450.00 (mb) 9431 1451 323 * M1: ER = 6.62 (MeV) EG = 4.00 (MeV) SIG = 3.30 (mb) 9431 1451 324 * E2: ER = 10.17 (MeV) EG = 3.25 (MeV) SIG = 6.79 (mb) 9431 1451 325 -------------------------------------------------------- 9431 1451 326 9431 1451 327 9431 1451 328 References 9431 1451 329 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9431 1451 330 2) F. Manero, V.A. Konshin: At. Energy Review, 10, 637 (1972). 9431 1451 331 3) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9431 1451 332 4) J.E.Gindler et al.: Phys. Rev., 115, 1217 (1959). 9431 1451 333 5) E.K.Hulet et al.: WASH-1033, 28 (1961). 9431 1451 334 6) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9431 1451 335 7) H.C.Britt, J.B.Wilhelmy: Nucl. Sci. Eng., 72, 222 (1979). 9431 1451 336 8) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9431 1451 337 9) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9431 1451 338 Japanese. 9431 1451 339 10) C.Kalbach: Phys. Rev. C33, 818 (1986). 9431 1451 340 11) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9431 1451 341 12) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9431 1451 342 13) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9431 1451 343 14) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9431 1451 344 15) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9431 1451 345 16) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9431 1451 346 9431 1451 347 1 451 359 19431 1451 348 2 151 4 19431 1451 349 3 4 36 19431 1451 350 3 16 13 19431 1451 351 3 17 8 19431 1451 352 3 18 119 19431 1451 353 3 102 141 19431 1451 354 8 4 2 19431 1451 355 8 16 2 19431 1451 356 8 17 2 19431 1451 357 8 18 2 19431 1451 358 8 102 2 19431 1451 359 9431 1 099999 9431 0 0 0 9.423700+4 2.350120+2 0 0 1 09431 2151 1 9.423700+4 1.000000+0 0 0 1 09431 2151 2 1.000000-5 3.000000-1 0 0 0 09431 2151 3 3.500000+0 9.397000-1 0 0 0 09431 2151 4 9431 2 099999 9431 0 0 0 9.423700+4 2.350120+2 0 0 0 09431 3 4 1 0.000000+0-4.771000+4 0 0 1 979431 3 4 2 97 2 9431 3 4 3 4.791300+4 0.000000+0 5.000000+4 7.193170-3 7.000000+4 2.800470-29431 3 4 4 1.000000+5 5.579920-2 1.041060+5 5.931135-2 1.064510+5 6.131742-29431 3 4 5 1.200000+5 7.558733-2 1.400000+5 9.787048-2 1.461630+5 1.047812-19431 3 4 6 1.561110+5 1.154192-1 1.561120+5 1.154205-1 1.700000+5 1.330244-19431 3 4 7 1.757450+5 1.398400-1 2.000000+5 1.697749-1 2.020360+5 1.717405-19431 3 4 8 2.252040+5 2.073837-1 2.500000+5 2.555126-1 2.580940+5 2.673753-19431 3 4 9 2.814120+5 2.991871-1 3.000000+5 3.320790-1 3.052940+5 3.378403-19431 3 4 10 3.223360+5 3.639158-1 3.719760+5 4.340288-1 3.725790+5 4.349939-19431 3 4 11 4.000000+5 4.748561-1 4.059100+5 4.820144-1 4.095650+5 4.884878-19431 3 4 12 4.402750+5 5.339057-1 4.402760+5 5.339076-1 4.551280+5 5.582965-19431 3 4 13 4.755150+5 5.926489-1 4.880680+5 6.152103-1 5.000000+5 6.374067-19431 3 4 14 5.151830+5 6.538079-1 5.473190+5 6.878470-1 5.844760+5 7.162140-19431 3 4 15 5.935150+5 7.231526-1 6.000000+5 7.280753-1 6.577870+5 7.629173-19431 3 4 16 6.580880+5 7.634423-1 6.939400+5 7.865863-1 6.991620+5 7.902970-19431 3 4 17 7.000000+5 7.911672-1 7.190470+5 7.988365-1 7.441530+5 8.069954-19431 3 4 18 7.602210+5 8.119134-1 8.000000+5 8.193897-1 9.000000+5 8.352807-19431 3 4 19 1.000000+6 8.635332-1 1.100000+6 8.865314-1 1.200000+6 9.128476-19431 3 4 20 1.300000+6 9.408868-1 1.400000+6 9.704010-1 1.500000+6 9.997365-19431 3 4 21 1.600000+6 1.028678+0 1.700000+6 1.055278+0 1.800000+6 1.080897+09431 3 4 22 1.900000+6 1.102888+0 2.000000+6 1.123735+0 2.300000+6 1.169531+09431 3 4 23 2.500000+6 1.189641+0 2.700000+6 1.205716+0 3.000000+6 1.223223+09431 3 4 24 3.500000+6 1.232333+0 4.000000+6 1.215956+0 4.500000+6 1.192129+09431 3 4 25 5.000000+6 1.171681+0 5.500000+6 1.146990+0 6.000000+6 1.059844+09431 3 4 26 6.500000+6 8.980778-1 7.000000+6 7.652332-1 7.500000+6 6.685643-19431 3 4 27 8.000000+6 6.027104-1 8.500000+6 5.525225-1 9.000000+6 5.156824-19431 3 4 28 9.500000+6 4.849571-1 1.000000+7 4.601353-1 1.050000+7 4.383334-19431 3 4 29 1.100000+7 4.195020-1 1.150000+7 4.024959-1 1.200000+7 3.863705-19431 3 4 30 1.250000+7 3.717342-1 1.300000+7 3.576208-1 1.350000+7 3.445877-19431 3 4 31 1.400000+7 3.318724-1 1.450000+7 3.202910-1 1.500000+7 3.086548-19431 3 4 32 1.550000+7 2.981365-1 1.600000+7 2.878842-1 1.650000+7 2.783846-19431 3 4 33 1.700000+7 2.690770-1 1.750000+7 2.607599-1 1.800000+7 2.524273-19431 3 4 34 1.850000+7 2.451192-1 1.900000+7 2.375736-1 1.950000+7 2.311535-19431 3 4 35 2.000000+7 2.244431-1 9431 3 4 36 9431 3 099999 9.423700+4 2.350120+2 0 0 0 09431 3 16 1 -5.880730+6-5.880730+6 0 0 1 299431 3 16 2 29 2 9431 3 16 3 5.905750+6 0.000000+0 6.500000+6 1.313040-2 7.000000+6 4.448290-29431 3 16 4 7.500000+6 6.726340-2 8.000000+6 8.528630-2 8.500000+6 9.505810-29431 3 16 5 9.000000+6 1.036340-1 9.500000+6 1.115070-1 1.000000+7 1.203680-19431 3 16 6 1.050000+7 1.306610-1 1.100000+7 1.397850-1 1.150000+7 1.500020-19431 3 16 7 1.200000+7 1.613460-1 1.250000+7 1.652360-1 1.300000+7 1.632650-19431 3 16 8 1.350000+7 1.580220-1 1.400000+7 1.510520-1 1.450000+7 1.410490-19431 3 16 9 1.500000+7 1.342460-1 1.550000+7 1.281550-1 1.600000+7 1.200850-19431 3 16 10 1.650000+7 1.158610-1 1.700000+7 1.122670-1 1.750000+7 1.064250-19431 3 16 11 1.800000+7 1.038980-1 1.850000+7 9.890510-2 1.900000+7 9.704640-29431 3 16 12 1.950000+7 9.274990-2 2.000000+7 9.129810-2 9431 3 16 13 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