JENDL-5 (Neutron sublibrary (activation cs)) Am-244 0 0 0 0 9.524400+4 2.419680+2 0 0 6 19552 1451 1 0.000000+0 1.000000+0 0 0 0 69552 1451 2 1.000000+0 2.000000+7 0 0 10 59552 1451 3 2.936000+2 0.000000+0 4 0 351 149552 1451 4 95-Am-244 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9552 1451 5 DIST-DEC21 20100304 9552 1451 6 ----JENDL-5 MATERIAL 9552 9552 1451 7 -----INCIDENT NEUTRON DATA 9552 1451 8 ------ENDF-6 FORMAT 9552 1451 9 9552 1451 10 History 9552 1451 11 07-08 Theoretical calculation was performed with CCONE code. 9552 1451 12 07-10 Theoretical calculation was performed with CCONE code. 9552 1451 13 07-11 Data were compiled as JENDL/AC-2008/1/. 9552 1451 14 10-02 Data of prompt gamma rays due to fission were given. 9552 1451 15 10-03 Covariance data were given. 9552 1451 16 9552 1451 17 21-11 revised by O.Iwamoto 9552 1451 18 (MF3/MT19-21,38) deleted 9552 1451 19 (MF8/MT4,16-18,37,102) added 9552 1451 20 9552 1451 21 MF=1 General information 9552 1451 22 MT=452 Number of Neutrons per fission 9552 1451 23 Sum of MT's=455 and 456. 9552 1451 24 9552 1451 25 MT=455 Delayed neutron data 9552 1451 26 (Same as JENDL-3.3) 9552 1451 27 Estimated from Tuttle's systematics/2/. 9552 1451 28 9552 1451 29 MT=456 Number of prompt neutrons per fission 9552 1451 30 (Same as JENDL-3.3) 9552 1451 31 Estimated from Howerton's sytematics/3/. 9552 1451 32 9552 1451 33 9552 1451 34 MF= 2 Resonance parameters 9552 1451 35 MT=151 9552 1451 36 No resonance parameters are given. 9552 1451 37 9552 1451 38 9552 1451 39 Thermal cross sections and resonance integrals (at 300K) 9552 1451 40 ------------------------------------------------------- 9552 1451 41 0.0253 eV reson. integ.(*) 9552 1451 42 (barns) (barns) 9552 1451 43 ------------------------------------------------------- 9552 1451 44 total 3312.8 9552 1451 45 elastic 11.24 9552 1451 46 fission 2301.0 547 9552 1451 47 capture 1000.3 422 9552 1451 48 ------------------------------------------------------- 9552 1451 49 (*) In the energy range from 0.5 eV to 10 MeV. 9552 1451 50 9552 1451 51 9552 1451 52 MF= 3 Neutron cross sections 9552 1451 53 Below 0.15 eV: 9552 1451 54 Elastic scattering cross section is 11.2 b calculated from 9552 1451 55 scattering radius of 9.45fm/4/. 9552 1451 56 Fission cross section is in the 1/v shape, and 2300 b at 9552 1451 57 0.0253 eV/5/. 9552 1451 58 Capture cross section is in the 1/v shape, and 1000 b at 9552 1451 59 0.0253 eV which is about 1/2 of a value estimated from the 9552 1451 60 cross-section ratio of capture and fission at 1 eV and 9552 1451 61 thermal fission cross section. 9552 1451 62 9552 1451 63 Above 0.15 eV: 9552 1451 64 Cross sections were calculated with CCONE code/4/. 9552 1451 65 9552 1451 66 MT= 1 Total cross section 9552 1451 67 The cross section was calculated with CC OMP of Soukhovitskii 9552 1451 68 et al./6/ The OMP was adjusted by the Am-241(n,tot) cross 9552 1451 69 section/7/. 9552 1451 70 9552 1451 71 MT=18 Fission cross section 9552 1451 72 The simulated (n,f) cross sections of Britt and Wilhelmy/8/ 9552 1451 73 were used to determine the parameters in the CCONE 9552 1451 74 calculation. 9552 1451 75 9552 1451 76 9552 1451 77 MF= 4 Angular distributions of secondary neutrons 9552 1451 78 MT=2 Elastic scattering 9552 1451 79 Calculated with CCONE code. 9552 1451 80 9552 1451 81 MT=18 Fission 9552 1451 82 Isotropic distributions in the laboratory system were assumed.9552 1451 83 9552 1451 84 9552 1451 85 MF= 5 Energy distributions of secondary neutrons 9552 1451 86 MT=18 Prompt neutrons 9552 1451 87 Calculated with CCONE code/4/. 9552 1451 88 9552 1451 89 9552 1451 90 MF= 6 Energy-angle distributions 9552 1451 91 Calculated with CCONE code. 9552 1451 92 Distributions from fission (MT=18) are not included. 9552 1451 93 9552 1451 94 9552 1451 95 MF=12 Photon production multiplicities 9552 1451 96 MT=18 Fission 9552 1451 97 Calculated from the total energy released by the prompt 9552 1451 98 gamma-rays due to fission which was estimated from its 9552 1451 99 systematics, and the average energy of gamma-rays. 9552 1451 100 9552 1451 101 9552 1451 102 MF=14 Photon angular distributions 9552 1451 103 MT=18 Fission 9552 1451 104 Isotoropic distributions were assumed. 9552 1451 105 9552 1451 106 9552 1451 107 MF=15 Continuous photon energy spectra 9552 1451 108 MT=18 Fission 9552 1451 109 Experimental data measured by Verbinski et al./9/ for 9552 1451 110 Pu-239 thermal fission were adopted. 9552 1451 111 9552 1451 112 9552 1451 113 MF=31 Covariances of average number of neutrons per fission 9552 1451 114 MT=452 Number of neutrons per fission 9552 1451 115 Sum of covariances for MT=455 and MT=456. 9552 1451 116 9552 1451 117 MT=455 9552 1451 118 Error of 15% was assumed. 9552 1451 119 9552 1451 120 MT=456 9552 1451 121 Covariance was obtained by fitting a linear function to the 9552 1451 122 at 0.0 and 5.0 MeV with an uncertainty of 5%. 9552 1451 123 9552 1451 124 9552 1451 125 MF=33 Covariances of neutron cross sections 9552 1451 126 Covariances were given to all the cross sections by using 9552 1451 127 KALMAN code/10/ and the covariances of model parameters 9552 1451 128 used in the cross-section calculations. 9552 1451 129 9552 1451 130 Covariances of the fission cross section were determined from 9552 1451 131 experimental data. 9552 1451 132 9552 1451 133 For the following cross sections, standard deviations in the 9552 1451 134 energy region below 0.15 eV were assumed as follows: 9552 1451 135 9552 1451 136 Total 19 % 9552 1451 137 Elastic scattering 50 % 9552 1451 138 Fission 16 % estimated from experimental data 9552 1451 139 Capture 50 % 9552 1451 140 9552 1451 141 9552 1451 142 MF=34 Covariances for Angular Distributions 9552 1451 143 MT=2 Elastic scattering 9552 1451 144 Covariances were given only to P1 components. 9552 1451 145 9552 1451 146 9552 1451 147 MF=35 Covariances for Energy Distributions 9552 1451 148 MT=18 Fission spectra 9552 1451 149 Estimated with CCONE and KALMAN codes. 9552 1451 150 9552 1451 151 9552 1451 152 ***************************************************************** 9552 1451 153 Calculation with CCONE code 9552 1451 154 ***************************************************************** 9552 1451 155 9552 1451 156 Models and parameters used in the CCONE/4/ calculation 9552 1451 157 1) Coupled channel optical model 9552 1451 158 Levels in the rotational band were included. Optical model 9552 1451 159 potential and coupled levels are shown in Table 1. 9552 1451 160 9552 1451 161 2) Two-component exciton model/11/ 9552 1451 162 * Global parametrization of Koning-Duijvestijn/12/ 9552 1451 163 was used. 9552 1451 164 * Gamma emission channel/13/ was added to simulate direct 9552 1451 165 and semi-direct capture reaction. 9552 1451 166 9552 1451 167 3) Hauser-Feshbach statistical model 9552 1451 168 * Moldauer width fluctuation correction/14/ was included. 9552 1451 169 * Neutron, gamma and fission decay channel were included. 9552 1451 170 * Transmission coefficients of neutrons were taken from 9552 1451 171 coupled channel calculation in Table 1. 9552 1451 172 * The level scheme of the target is shown in Table 2. 9552 1451 173 * Level density formula of constant temperature and Fermi-gas 9552 1451 174 model were used with shell energy correction and collective 9552 1451 175 enhancement factor. Parameters are shown in Table 3. 9552 1451 176 * Fission channel: 9552 1451 177 Double humped fission barriers were assumed. 9552 1451 178 Fission barrier penetrabilities were calculated with 9552 1451 179 Hill-Wheler formula/15/. Fission barrier parameters were 9552 1451 180 shown in Table 4. Transition state model was used and 9552 1451 181 continuum levels are assumed above the saddles. The level 9552 1451 182 density parameters for inner and outer saddles are shown in 9552 1451 183 Tables 5 and 6, respectively. 9552 1451 184 * Gamma-ray strength function of Kopecky et al/16/,/17/ 9552 1451 185 was used. The prameters are shown in Table 7. 9552 1451 186 9552 1451 187 9552 1451 188 ------------------------------------------------------------------9552 1451 189 Tables 9552 1451 190 ------------------------------------------------------------------9552 1451 191 9552 1451 192 Table 1. Coupled channel calculation 9552 1451 193 -------------------------------------------------- 9552 1451 194 * rigid rotor model was applied 9552 1451 195 * coupled levels = 0,1,6 (see Table 2) 9552 1451 196 * optical potential parameters /6/ 9552 1451 197 Volume: 9552 1451 198 V_0 = 48 MeV 9552 1451 199 lambda_HF = 0.004 1/MeV 9552 1451 200 C_viso = 15.9 MeV 9552 1451 201 A_v = 12.04 MeV 9552 1451 202 B_v = 81.36 MeV 9552 1451 203 E_a = 385 MeV 9552 1451 204 r_v = 1.255 fm 9552 1451 205 a_v = 0.58 fm 9552 1451 206 Surface: 9552 1451 207 W_0 = 17.2 MeV 9552 1451 208 B_s = 11.19 MeV 9552 1451 209 C_s = 0.01361 1/MeV 9552 1451 210 C_wiso = 23.5 MeV 9552 1451 211 r_s = 1.15 fm 9552 1451 212 a_s = 0.601 fm 9552 1451 213 Spin-orbit: 9552 1451 214 V_so = 5.75 MeV 9552 1451 215 lambda_so = 0.005 1/MeV 9552 1451 216 W_so = -3.1 MeV 9552 1451 217 B_so = 160 MeV 9552 1451 218 r_so = 1.1214 fm 9552 1451 219 a_so = 0.59 fm 9552 1451 220 Coulomb: 9552 1451 221 C_coul = 1.3 9552 1451 222 r_c = 1.2452 fm 9552 1451 223 a_c = 0.545 fm 9552 1451 224 Deformation: 9552 1451 225 beta_2 = 0.213 9552 1451 226 beta_4 = 0.08 9552 1451 227 beta_6 = 0.0015 9552 1451 228 9552 1451 229 * Calculated strength function 9552 1451 230 S0= 0.82e-4 S1= 2.20e-4 R'= 9.45 fm (En=1 keV) 9552 1451 231 -------------------------------------------------- 9552 1451 232 9552 1451 233 Table 2. Level Scheme of Am-244 9552 1451 234 ------------------- 9552 1451 235 No. Ex(MeV) J PI 9552 1451 236 ------------------- 9552 1451 237 0 0.00000 6 - * 9552 1451 238 1 0.07200 7 - * 9552 1451 239 2 0.08610 1 + 9552 1451 240 3 0.09840 2 + 9552 1451 241 4 0.12140 3 + 9552 1451 242 5 0.14640 4 + 9552 1451 243 6 0.15600 8 - * 9552 1451 244 7 0.17380 1 - 9552 1451 245 8 0.18160 5 + 9552 1451 246 9 0.19540 2 - 9552 1451 247 10 0.22640 3 - 9552 1451 248 11 0.25980 2 - 9552 1451 249 12 0.27030 4 - 9552 1451 250 13 0.28730 1 - 9552 1451 251 14 0.29480 3 - 9552 1451 252 15 0.32090 5 - 9552 1451 253 16 0.33370 0 - 9552 1451 254 17 0.34080 3 - 9552 1451 255 18 0.34180 4 - 9552 1451 256 19 0.34650 3 + 9552 1451 257 20 0.35990 2 - 9552 1451 258 21 0.36500 5 - 9552 1451 259 22 0.36570 1 + 9552 1451 260 23 0.37520 0 + 9552 1451 261 24 0.38810 4 + 9552 1451 262 25 0.39680 5 - 9552 1451 263 26 0.41280 2 + 9552 1451 264 27 0.41710 2 + 9552 1451 265 28 0.41820 2 + 9552 1451 266 29 0.41930 3 - 9552 1451 267 30 0.42910 3 - 9552 1451 268 31 0.43100 3 - 9552 1451 269 32 0.43310 4 - 9552 1451 270 33 0.43540 5 - 9552 1451 271 34 0.44250 3 + 9552 1451 272 35 0.44700 5 + 9552 1451 273 36 0.45210 1 + 9552 1451 274 ------------------- 9552 1451 275 *) Coupled levels in CC calculation 9552 1451 276 9552 1451 277 Table 3. Level density parameters 9552 1451 278 -------------------------------------------------------- 9552 1451 279 Nuclide a* Pair Eshell T E0 Ematch 9552 1451 280 1/MeV MeV MeV MeV MeV MeV 9552 1451 281 -------------------------------------------------------- 9552 1451 282 Am-245 18.8322 0.7667 2.4550 0.4036 -1.1596 3.3413 9552 1451 283 Am-244 18.7661 0.0000 1.9765 0.2583 -0.5425 0.8000 9552 1451 284 Am-243 18.6999 0.7698 2.0985 0.3873 -0.8965 3.0385 9552 1451 285 Am-242 18.6337 0.0000 1.6845 0.2795 -0.6541 0.9592 9552 1451 286 Am-241 18.1961 0.7730 1.7328 0.3819 -0.7226 2.8365 9552 1451 287 -------------------------------------------------------- 9552 1451 288 9552 1451 289 Table 4. Fission barrier parameters 9552 1451 290 ---------------------------------------- 9552 1451 291 Nuclide V_A hw_A V_B hw_B 9552 1451 292 MeV MeV MeV MeV 9552 1451 293 ---------------------------------------- 9552 1451 294 Am-245 6.200 0.800 5.200 0.520 9552 1451 295 Am-244 6.450 0.650 6.000 0.530 9552 1451 296 Am-243 6.200 0.800 5.400 0.520 9552 1451 297 Am-242 6.510 0.600 6.050 0.550 9552 1451 298 Am-241 6.100 0.800 5.500 0.520 9552 1451 299 ---------------------------------------- 9552 1451 300 9552 1451 301 Table 5. Level density above inner saddle 9552 1451 302 -------------------------------------------------------- 9552 1451 303 Nuclide a* Pair Eshell T E0 Ematch 9552 1451 304 1/MeV MeV MeV MeV MeV MeV 9552 1451 305 -------------------------------------------------------- 9552 1451 306 Am-245 21.6571 0.8944 2.6000 0.2964 -1.1798 2.5944 9552 1451 307 Am-244 21.5810 0.0000 2.6000 0.3194 -2.3947 2.0000 9552 1451 308 Am-243 21.5049 0.8981 2.6000 0.3201 -1.4966 2.8981 9552 1451 309 Am-242 20.8697 0.0000 2.6000 0.3254 -2.4113 2.0000 9552 1451 310 Am-241 21.3526 0.9018 2.6000 0.3213 -1.4929 2.9018 9552 1451 311 -------------------------------------------------------- 9552 1451 312 9552 1451 313 Table 6. Level density above outer saddle 9552 1451 314 -------------------------------------------------------- 9552 1451 315 Nuclide a* Pair Eshell T E0 Ematch 9552 1451 316 1/MeV MeV MeV MeV MeV MeV 9552 1451 317 -------------------------------------------------------- 9552 1451 318 Am-245 21.6571 0.8944 0.6800 0.3203 -0.4723 2.4944 9552 1451 319 Am-244 21.5810 0.0000 0.6400 0.3664 -1.8698 2.2000 9552 1451 320 Am-243 21.5049 0.8981 0.6000 0.3532 -0.8019 2.8981 9552 1451 321 Am-242 21.4288 0.0000 0.5600 0.3688 -1.8681 2.2000 9552 1451 322 Am-241 21.3526 0.9018 0.5200 0.3556 -0.7969 2.9018 9552 1451 323 -------------------------------------------------------- 9552 1451 324 9552 1451 325 Table 7. Gamma-ray strength function for Am-245 9552 1451 326 -------------------------------------------------------- 9552 1451 327 * E1: ER = 11.50 (MeV) EG = 2.76 (MeV) SIG = 246.89 (mb) 9552 1451 328 ER = 14.28 (MeV) EG = 4.17 (MeV) SIG = 493.78 (mb) 9552 1451 329 * M1: ER = 6.55 (MeV) EG = 4.00 (MeV) SIG = 1.29 (mb) 9552 1451 330 * E2: ER = 10.07 (MeV) EG = 3.17 (MeV) SIG = 6.92 (mb) 9552 1451 331 -------------------------------------------------------- 9552 1451 332 9552 1451 333 9552 1451 334 References 9552 1451 335 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9552 1451 336 2) R.J.Tuttle: INDC(NDS)-107/G+Special, p.29 (1979). 9552 1451 337 3) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9552 1451 338 4) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9552 1451 339 5) S.E.Vandenbosch, J.Gray Jr.: J. Inorg. Nucl. Chem., 23, 9552 1451 340 187 (1961) 9552 1451 341 6) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9552 1451 342 7) T.W.Phillips, R.E.Howe: Nucl. Sci. Eng., 69, 375 (1979). 9552 1451 343 8) H.C.Britt, J.B.Wilhelmy: Nucl. Sci. Eng., 72, 222 (1979). 9552 1451 344 9) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9552 1451 345 10) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9552 1451 346 Japanese. 9552 1451 347 11) C.Kalbach: Phys. Rev. C33, 818 (1986). 9552 1451 348 12) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9552 1451 349 13) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9552 1451 350 14) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9552 1451 351 15) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9552 1451 352 16) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9552 1451 353 17) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9552 1451 354 9552 1451 355 1 451 369 19552 1451 356 2 151 4 19552 1451 357 3 4 37 19552 1451 358 3 16 14 19552 1451 359 3 17 9 19552 1451 360 3 18 123 19552 1451 361 3 37 5 19552 1451 362 3 102 152 19552 1451 363 8 4 2 19552 1451 364 8 16 2 19552 1451 365 8 17 2 19552 1451 366 8 18 2 19552 1451 367 8 37 2 19552 1451 368 8 102 2 19552 1451 369 9552 1 099999 9552 0 0 0 9.524400+4 2.419680+2 0 0 1 09552 2151 1 9.524400+4 1.000000+0 0 0 1 09552 2151 2 1.000000-5 1.500000-1 0 0 0 09552 2151 3 6.000000+0 9.450000-1 0 0 0 09552 2151 4 9552 2 099999 9552 0 0 0 9.524400+4 2.419680+2 0 0 0 09552 3 4 1 0.000000+0-7.200000+4 0 0 1 1019552 3 4 2 101 2 9552 3 4 3 7.229760+4 0.000000+0 8.645580+4 3.310360-2 9.880670+4 5.519831-29552 3 4 4 1.000000+5 5.730912-2 1.109110+5 7.373111-2 1.200000+5 8.741407-29552 3 4 5 1.219020+5 9.014153-2 1.400000+5 1.144100-1 1.470050+5 1.231877-19552 3 4 6 1.566450+5 1.406361-1 1.700000+5 1.657560-1 1.745180+5 1.739870-19552 3 4 7 1.823500+5 1.881792-1 1.823510+5 1.881810-1 1.962080+5 2.318779-19552 3 4 8 2.000000+5 2.414403-1 2.273360+5 2.893879-1 2.500000+5 3.241800-19552 3 4 9 2.608740+5 3.394705-1 2.714170+5 3.535417-1 2.884870+5 3.766239-19552 3 4 10 2.960180+5 3.865643-1 3.000000+5 3.919550-1 3.222260+5 4.079252-19552 3 4 11 3.350790+5 4.222803-1 3.422080+5 4.293253-1 3.432130+5 4.303498-19552 3 4 12 3.479320+5 4.355886-1 3.613870+5 4.497671-1 3.665080+5 4.549811-19552 3 4 13 3.672110+5 4.564655-1 3.767510+5 4.686747-1 3.897040+5 4.834620-19552 3 4 14 3.984400+5 4.943593-1 4.000000+5 4.971602-1 4.145060+5 5.169858-19552 3 4 15 4.188240+5 5.226256-1 4.199280+5 5.240517-1 4.210330+5 5.254756-19552 3 4 16 4.308730+5 5.378723-1 4.327810+5 5.402758-1 4.348900+5 5.429523-19552 3 4 17 4.371990+5 5.460859-1 4.443290+5 5.573701-1 4.488470+5 5.639659-19552 3 4 18 4.539680+5 5.738194-1 5.000000+5 6.398875-1 6.000000+5 7.656966-19552 3 4 19 7.000000+5 9.693271-1 8.000000+5 1.153045+0 9.000000+5 1.327410+09552 3 4 20 1.000000+6 1.493491+0 1.100000+6 1.626392+0 1.200000+6 1.742447+09552 3 4 21 1.300000+6 1.846032+0 1.400000+6 1.935080+0 1.500000+6 2.014184+09552 3 4 22 1.600000+6 2.081539+0 1.700000+6 2.136507+0 1.800000+6 2.182274+09552 3 4 23 1.900000+6 2.214425+0 2.000000+6 2.239745+0 2.100000+6 2.251477+09552 3 4 24 2.300000+6 2.260142+0 2.500000+6 2.242120+0 2.700000+6 2.212249+09552 3 4 25 3.000000+6 2.156362+0 3.500000+6 2.071485+0 4.000000+6 1.997799+09552 3 4 26 4.500000+6 1.944681+0 5.000000+6 1.908886+0 5.500000+6 1.894947+09552 3 4 27 6.000000+6 1.789022+0 6.500000+6 1.494739+0 7.000000+6 1.193626+09552 3 4 28 7.500000+6 9.383245-1 8.000000+6 7.744041-1 8.500000+6 6.520529-19552 3 4 29 9.000000+6 5.692510-1 9.500000+6 5.085168-1 1.000000+7 4.724304-19552 3 4 30 1.050000+7 4.433139-1 1.100000+7 4.159296-1 1.150000+7 3.968849-19552 3 4 31 1.200000+7 3.802016-1 1.250000+7 3.651246-1 1.300000+7 3.508278-19552 3 4 32 1.350000+7 3.411880-1 1.400000+7 3.275022-1 1.450000+7 3.150888-19552 3 4 33 1.500000+7 3.026047-1 1.550000+7 2.945761-1 1.600000+7 2.834018-19552 3 4 34 1.650000+7 2.758557-1 1.700000+7 2.658567-1 1.750000+7 2.589774-19552 3 4 35 1.800000+7 2.493668-1 1.850000+7 2.436036-1 1.900000+7 2.372296-19552 3 4 36 1.950000+7 2.295850-1 2.000000+7 2.236936-1 9552 3 4 37 9552 3 099999 9.524400+4 2.419680+2 0 0 0 09552 3 16 1 -5.366480+6-5.366480+6 0 0 1 319552 3 16 2 31 2 9552 3 16 3 5.388650+6 0.000000+0 5.500000+6 1.233810-4 6.000000+6 1.035020-19552 3 16 4 6.500000+6 3.533040-1 7.000000+6 5.185520-1 7.500000+6 6.210580-19552 3 16 5 8.000000+6 6.558650-1 8.500000+6 6.729730-1 9.000000+6 6.847430-19552 3 16 6 9.500000+6 6.892910-1 1.000000+7 6.844570-1 1.050000+7 6.836860-19552 3 16 7 1.100000+7 6.991500-1 1.150000+7 7.040690-1 1.200000+7 6.980640-19552 3 16 8 1.250000+7 6.691380-1 1.300000+7 6.188960-1 1.350000+7 5.497790-19552 3 16 9 1.400000+7 4.872670-1 1.450000+7 4.285680-1 1.500000+7 3.786570-19552 3 16 10 1.550000+7 3.306570-1 1.600000+7 2.991270-1 1.650000+7 2.674540-19552 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