JENDL-5 (Neutron sublibrary (activation cs)) Pu-236 0 0 0 0 9.423600+4 2.340180+2 0 0 6 19428 1451 1 0.000000+0 1.000000+0 0 0 0 69428 1451 2 1.000000+0 2.000000+7 0 0 10 59428 1451 3 2.936000+2 0.000000+0 4 0 364 129428 1451 4 94-Pu-236 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9428 1451 5 DIST-DEC21 20100318 9428 1451 6 ----JENDL-5 MATERIAL 9428 9428 1451 7 -----INCIDENT NEUTRON DATA 9428 1451 8 ------ENDF-6 FORMAT 9428 1451 9 9428 1451 10 History 9428 1451 11 06-04 Resonance parameters and fission cross section were revised.9428 1451 12 07-02 Theoretical calculation was made with CCONE code. 9428 1451 13 07-05 Re-calculation with CCONE code was made. 9428 1451 14 Data were compiled as JENDL/AC-2008/1/. 9428 1451 15 09-02 (1,452), (1,455) and (1,456) were revised. 9428 1451 16 10-02 Data of prompt gamma rays due to fission were given. 9428 1451 17 10-03 Covariance data were given. 9428 1451 18 9428 1451 19 21-11 revised by O.Iwamoto 9428 1451 20 (MF3/MT19-21,38) deleted 9428 1451 21 (MF8/MT16-18,102) JENDL/AD-2017 adopted 9428 1451 22 (MF8/MT4) added 9428 1451 23 9428 1451 24 MF= 1 General information 9428 1451 25 MT=452 Number of Neutrons per fission 9428 1451 26 Sum of MT's = 455 and 456. 9428 1451 27 9428 1451 28 MT=455 Delayed neutron data 9428 1451 29 Average values of systematics by Tuttle/2/, Benedetti et al. 9428 1451 30 /3/ and Waldo et al./4/, and partial fission cross sections 9428 1451 31 calculated with CCONE code/5/ 9428 1451 32 Decay constants were assumed to be the same as those of Pu-2389428 1451 33 calculated by Brady and England/6/. 9428 1451 34 9428 1451 35 MT=456 Number of prompt neutrons per fission 9428 1451 36 Based on systematics by Ohsawa/7/. 9428 1451 37 9428 1451 38 MF= 2 Resonance parameters 9428 1451 39 MT=151 9428 1451 40 Resolved resonance parameters (below 10 eV) 9428 1451 41 The resonance parameters of ENDF/B-VI were adopted and those 9428 1451 42 of a negative resonance were modified to reproduce the thermal9428 1451 43 fission cross section of 141+-15 b which were derived from the9428 1451 44 experimental data of Gindler et al./8/, Hulet et al./9/, 9428 1451 45 Belyaev et al./10/ 9428 1451 46 9428 1451 47 Unresolved resonance parameters (10 eV - 40 keV) 9428 1451 48 Parameters were determined with ASREP code/11/ to reproduce 9428 1451 49 the fission cross section determined from the experimental 9428 1451 50 data/12,13/, and total and capture cross sections calculated 9428 1451 51 with CCONE code/5/. The parameters are used only for self- 9428 1451 52 shielding calculations. 9428 1451 53 9428 1451 54 Thermal cross sections and resonance integrals (at 300K) 9428 1451 55 ------------------------------------------------------- 9428 1451 56 0.0253 eV reson. integ.(*) 9428 1451 57 (barns) (barns) 9428 1451 58 ------------------------------------------------------- 9428 1451 59 total 176.72 9428 1451 60 elastic 9.20 9428 1451 61 fission 139.96 971 9428 1451 62 capture 27.56 248 9428 1451 63 ------------------------------------------------------- 9428 1451 64 (*) In the energy range from 0.5 eV to 10 MeV. 9428 1451 65 9428 1451 66 9428 1451 67 MF= 3 Neutron cross sections 9428 1451 68 Cross sections above the resolved resonance region except for 9428 1451 69 the elastic scattering (MT=2) and fission cross sections (MT=18,9428 1451 70 19, 20, 21, 38) were calculated with CCONE code/5/. 9428 1451 71 9428 1451 72 MT= 1 Total cross section 9428 1451 73 The cross section was calculated with CC OMP of Soukhovitskii 9428 1451 74 et al./14/ 9428 1451 75 9428 1451 76 MT=2 Elastic scattering cross section 9428 1451 77 Calculated as total - non-elstic scattering cross sections 9428 1451 78 9428 1451 79 MT=18 Fission cross section 9428 1451 80 The following experimental data were analyzed in the energy 9428 1451 81 range from 100 eV to 4 MeV with the GMA code/15/: 9428 1451 82 9428 1451 83 Authors Energy range Data points Reference 9428 1451 84 Gromova+ 7.14 eV - 5.78 MeV 106 /12/ 9428 1451 85 Gerasimov+ 15.8 eV - 34 keV 9 /13/ 9428 1451 86 9428 1451 87 Below 80 eV, resonance structure was reproduced by eye- 9428 1451 88 guiding. Avove 5.5 MeV, cross sections calculated with CCONE 9428 1451 89 code were adopted. 9428 1451 90 9428 1451 91 The simulated (n,f) cross sections of Britt and Wilhelmy/16/, 9428 1451 92 and the experimental data of Gromova et al./12/, Gerasimov et 9428 1451 93 al./13/ and Vorotnikov et al./17/ were used to determine 9428 1451 94 the parameters in the CCONE calculation. 9428 1451 95 9428 1451 96 MT=19, 20, 21, 38 Multi-chance fission cross sections 9428 1451 97 Calculated with CCONE code, and renormalized to the total 9428 1451 98 fission cross section (MT=18). 9428 1451 99 9428 1451 100 9428 1451 101 MF= 4 Angular distributions of secondary neutrons 9428 1451 102 MT=2 Elastic scattering 9428 1451 103 Calculated with CCONE code. 9428 1451 104 9428 1451 105 MT=18 Fission 9428 1451 106 Isotropic distributions in the laboratory system were assumed.9428 1451 107 9428 1451 108 9428 1451 109 MF= 5 Energy distributions of secondary neutrons 9428 1451 110 MT=18 Prompt fission neutrons 9428 1451 111 Calculated with CCONE code. 9428 1451 112 9428 1451 113 9428 1451 114 MF= 6 Energy-angle distributions 9428 1451 115 Calculated with CCONE code. 9428 1451 116 Distributions from fission (MT=18) are not included. 9428 1451 117 9428 1451 118 9428 1451 119 MF=12 Photon production multiplicities 9428 1451 120 MT=18 Fission 9428 1451 121 Calculated from the total energy released by the prompt 9428 1451 122 gamma-rays due to fission which was estimated from its 9428 1451 123 systematics, and the average energy of gamma-rays. 9428 1451 124 9428 1451 125 9428 1451 126 MF=14 Photon angular distributions 9428 1451 127 MT=18 Fission 9428 1451 128 Isotoropic distributions were assumed. 9428 1451 129 9428 1451 130 9428 1451 131 MF=15 Continuous photon energy spectra 9428 1451 132 MT=18 Fission 9428 1451 133 Experimental data measured by Verbinski et al./18/ for 9428 1451 134 Pu-239 thermal fission were adopted. 9428 1451 135 9428 1451 136 9428 1451 137 MF=31 Covariances of average number of neutrons per fission 9428 1451 138 MT=452 Number of neutrons per fission 9428 1451 139 Sum of covariances for MT=455 and MT=456. 9428 1451 140 9428 1451 141 MT=455 9428 1451 142 Error of 15% was assumed. 9428 1451 143 9428 1451 144 MT=456 9428 1451 145 Covariance was obtained by fitting a linear function to the 9428 1451 146 data at 0.0 and 5.0 MeV with an uncertainty of 5%. 9428 1451 147 9428 1451 148 9428 1451 149 MF=32 Covariances of resonance parameters 9428 1451 150 MT=151 Resolved resonance parameterss 9428 1451 151 Format of LCOMP=0 was adopted. 9428 1451 152 9428 1451 153 Uncertainties of parameters were assumed as follows: 9428 1451 154 Resonance energy 0.1 % 9428 1451 155 Neutron width 10 % 9428 1451 156 Capture width 50 % 9428 1451 157 Fission width 20 % 9428 1451 158 9428 1451 159 They were further modified by considering experimental data 9428 1451 160 of the fission cross section at the thermal neutron energy. 9428 1451 161 9428 1451 162 9428 1451 163 MF=33 Covariances of neutron cross sections 9428 1451 164 Covariances were given to all the cross sections by using 9428 1451 165 KALMAN code/19/ and the covariances of model parameters 9428 1451 166 used in the cross-section calculations. 9428 1451 167 9428 1451 168 For the fission cross section, covariances obtained with the 9428 1451 169 GMA analysis were adopted. Standard deviations (SD) were 9428 1451 170 multiplied by a factor of 1.5. SD's of 15% were assumed in the 9428 1451 171 energy region below 86 eV and above 4 MeV. 9428 1451 172 9428 1451 173 In the resolved resonance region, the following standard 9428 1451 174 deviations were added to the contributions from resonance 9428 1451 175 parameters: 9428 1451 176 Total 2 b 9428 1451 177 Elastic scattering 20 % 9428 1451 178 9428 1451 179 9428 1451 180 MF=34 Covariances for Angular Distributions 9428 1451 181 MT=2 Elastic scattering 9428 1451 182 Covariances were given only to P1 components. 9428 1451 183 9428 1451 184 9428 1451 185 MF=35 Covariances for Energy Distributions 9428 1451 186 MT=18 Fission spectra 9428 1451 187 Estimated with CCONE and KALMAN codes. 9428 1451 188 9428 1451 189 9428 1451 190 ***************************************************************** 9428 1451 191 Calculation with CCONE code 9428 1451 192 ***************************************************************** 9428 1451 193 9428 1451 194 Models and parameters used in the CCONE/5/ calculation 9428 1451 195 1) Coupled channel optical model 9428 1451 196 Levels in the rotational band were included. Optical model 9428 1451 197 potential and coupled levels are shown in Table 1. 9428 1451 198 9428 1451 199 2) Two-component exciton model/20/ 9428 1451 200 * Global parametrization of Koning-Duijvestijn/21/ 9428 1451 201 was used. 9428 1451 202 * Gamma emission channel/22/ was added to simulate direct 9428 1451 203 and semi-direct capture reaction. 9428 1451 204 9428 1451 205 3) Hauser-Feshbach statistical model 9428 1451 206 * Moldauer width fluctuation correction/23/ was included. 9428 1451 207 * Neutron, gamma and fission decay channel were included. 9428 1451 208 * Transmission coefficients of neutrons were taken from 9428 1451 209 coupled channel calculation in Table 1. 9428 1451 210 * The level scheme of the target is shown in Table 2. 9428 1451 211 * Level density formula of constant temperature and Fermi-gas 9428 1451 212 model were used with shell energy correction and collective 9428 1451 213 enhancement factor. Parameters are shown in Table 3. 9428 1451 214 * Fission channel: 9428 1451 215 Double humped fission barriers were assumed. 9428 1451 216 Fission barrier penetrabilities were calculated with 9428 1451 217 Hill-Wheler formula/24/. Fission barrier parameters were 9428 1451 218 shown in Table 4. Transition state model was used and 9428 1451 219 continuum levels are assumed above the saddles. The level 9428 1451 220 density parameters for inner and outer saddles are shown in 9428 1451 221 Tables 5 and 6, respectively. 9428 1451 222 * Gamma-ray strength function of Kopecky et al/25/,/26/ 9428 1451 223 was used. The prameters are shown in Table 7. 9428 1451 224 9428 1451 225 9428 1451 226 ------------------------------------------------------------------9428 1451 227 Tables 9428 1451 228 ------------------------------------------------------------------9428 1451 229 9428 1451 230 Table 1. Coupled channel calculation 9428 1451 231 -------------------------------------------------- 9428 1451 232 * rigid rotor model was applied 9428 1451 233 * coupled levels = 0,1,2,3,4 (see Table 2) 9428 1451 234 * optical potential parameters /14/ 9428 1451 235 Volume: 9428 1451 236 V_0 = 49.97 MeV 9428 1451 237 lambda_HF = 0.01004 1/MeV 9428 1451 238 C_viso = 15.9 MeV 9428 1451 239 A_v = 12.04 MeV 9428 1451 240 B_v = 81.36 MeV 9428 1451 241 E_a = 385 MeV 9428 1451 242 r_v = 1.2568 fm 9428 1451 243 a_v = 0.633 fm 9428 1451 244 Surface: 9428 1451 245 W_0 = 17.2 MeV 9428 1451 246 B_s = 11.19 MeV 9428 1451 247 C_s = 0.01361 1/MeV 9428 1451 248 C_wiso = 23.5 MeV 9428 1451 249 r_s = 1.1803 fm 9428 1451 250 a_s = 0.601 fm 9428 1451 251 Spin-orbit: 9428 1451 252 V_so = 5.75 MeV 9428 1451 253 lambda_so = 0.005 1/MeV 9428 1451 254 W_so = -3.1 MeV 9428 1451 255 B_so = 160 MeV 9428 1451 256 r_so = 1.1214 fm 9428 1451 257 a_so = 0.59 fm 9428 1451 258 Coulomb: 9428 1451 259 C_coul = 1.3 9428 1451 260 r_c = 1.2452 fm 9428 1451 261 a_c = 0.545 fm 9428 1451 262 Deformation: 9428 1451 263 beta_2 = 0.21978 9428 1451 264 beta_4 = 0.07414 9428 1451 265 beta_6 = -0.00968 9428 1451 266 9428 1451 267 * Calculated strength function 9428 1451 268 S0= 1.11e-4 S1= 2.50e-4 R'= 9.45 fm (En=1 keV) 9428 1451 269 -------------------------------------------------- 9428 1451 270 9428 1451 271 Table 2. Level Scheme of Pu-236 9428 1451 272 ------------------- 9428 1451 273 No. Ex(MeV) J PI 9428 1451 274 ------------------- 9428 1451 275 0 0.00000 0 + * 9428 1451 276 1 0.04463 2 + * 9428 1451 277 2 0.14745 4 + * 9428 1451 278 3 0.30580 6 + * 9428 1451 279 4 0.51570 8 + * 9428 1451 280 5 0.77350 10 + 9428 1451 281 ------------------- 9428 1451 282 *) Coupled levels in CC calculation 9428 1451 283 9428 1451 284 Table 3. Level density parameters 9428 1451 285 -------------------------------------------------------- 9428 1451 286 Nuclide a* Pair Eshell T E0 Ematch 9428 1451 287 1/MeV MeV MeV MeV MeV MeV 9428 1451 288 -------------------------------------------------------- 9428 1451 289 Pu-237 18.3022 0.7795 1.8799 0.3586 -0.5090 2.5865 9428 1451 290 Pu-236 18.2358 1.5623 1.9752 0.3737 0.1216 3.5619 9428 1451 291 Pu-235 18.1694 0.7828 1.9791 0.3502 -0.4208 2.4828 9428 1451 292 Pu-234 18.1029 1.5689 2.1707 0.3732 0.1282 3.5689 9428 1451 293 -------------------------------------------------------- 9428 1451 294 9428 1451 295 Table 4. Fission barrier parameters 9428 1451 296 ---------------------------------------- 9428 1451 297 Nuclide V_A hw_A V_B hw_B 9428 1451 298 MeV MeV MeV MeV 9428 1451 299 ---------------------------------------- 9428 1451 300 Pu-237 5.800 0.800 5.800 0.520 9428 1451 301 Pu-236 6.000 1.040 5.000 0.600 9428 1451 302 Pu-235 6.000 0.800 5.000 0.520 9428 1451 303 Pu-234 5.600 1.040 4.600 0.600 9428 1451 304 ---------------------------------------- 9428 1451 305 9428 1451 306 Table 5. Level density above inner saddle 9428 1451 307 -------------------------------------------------------- 9428 1451 308 Nuclide a* Pair Eshell T E0 Ematch 9428 1451 309 1/MeV MeV MeV MeV MeV MeV 9428 1451 310 -------------------------------------------------------- 9428 1451 311 Pu-237 20.1324 0.9094 2.6000 0.3320 -1.5137 2.9094 9428 1451 312 Pu-236 20.0594 1.8226 2.6000 0.3326 -0.6004 3.8226 9428 1451 313 Pu-235 19.9863 0.9133 2.6000 0.3333 -1.5098 2.9133 9428 1451 314 Pu-234 19.9132 1.8304 2.6000 0.3339 -0.5927 3.8304 9428 1451 315 -------------------------------------------------------- 9428 1451 316 9428 1451 317 Table 6. Level density above outer saddle 9428 1451 318 -------------------------------------------------------- 9428 1451 319 Nuclide a* Pair Eshell T E0 Ematch 9428 1451 320 1/MeV MeV MeV MeV MeV MeV 9428 1451 321 -------------------------------------------------------- 9428 1451 322 Pu-237 20.1324 0.9094 0.3000 0.3706 -0.7963 2.9094 9428 1451 323 Pu-236 20.0594 1.8226 0.2600 0.3719 0.1175 3.8226 9428 1451 324 Pu-235 19.9863 0.9133 0.2200 0.3732 -0.7913 2.9133 9428 1451 325 Pu-234 19.9132 1.8304 0.1800 0.3744 0.1264 3.8304 9428 1451 326 -------------------------------------------------------- 9428 1451 327 9428 1451 328 Table 7. Gamma-ray strength function for Pu-237 9428 1451 329 -------------------------------------------------------- 9428 1451 330 K0 = 1.501 E0 = 4.500 (MeV) 9428 1451 331 * E1: ER = 10.90 (MeV) EG = 2.50 (MeV) SIG = 300.00 (mb) 9428 1451 332 ER = 13.80 (MeV) EG = 4.70 (MeV) SIG = 450.00 (mb) 9428 1451 333 * M1: ER = 6.63 (MeV) EG = 4.00 (MeV) SIG = 2.67 (mb) 9428 1451 334 * E2: ER = 10.18 (MeV) EG = 3.27 (MeV) SIG = 6.80 (mb) 9428 1451 335 -------------------------------------------------------- 9428 1451 336 9428 1451 337 9428 1451 338 References 9428 1451 339 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9428 1451 340 2) R.J.Tuttle: INDC(NDS)-107/G+Special, p.29 (1979). 9428 1451 341 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 9428 1451 342 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 9428 1451 343 5) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9428 1451 344 6) M.C.Brady, T.R.England: Nucl. Sci. Eng., 103, 129 (1989). 9428 1451 345 7) T.Ohsawa: J.Nucl. Radiochem. Sci., 9, 19 (2008). 9428 1451 346 8) J.E.Gindler et al.: Phys. Rev., 115, 1271 (1959). 9428 1451 347 9) E.K.Hulet et al.: WASH-1033, p.28 (1961). 9428 1451 348 10) B.N.Belyaev et al.: Sov. At. Energy, 68, 332 (1990). 9428 1451 349 11) Y.Kikuchi et al.: JAERI-Data/Code 99-025 (1999) in Japanese. 9428 1451 350 12) E.A.Gromova et al.: Sov. At. Energy, 68, 223 (1990). 9428 1451 351 13) V.F.Gerasimov et al.: JINR-E3-97-213, p.348 (1997). 9428 1451 352 14) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9428 1451 353 15) W.P.Poenitz: BNL-NCS-51363, Vol.I, p.249 (1981). 9428 1451 354 S.Chiba, D.L.Smith: ANL/NDM-121 (1991). 9428 1451 355 16) H.C.Britt, J.B.Wilhelmy: Nucl. Sci. Eng., 72, 222 (1979). 9428 1451 356 17) P.E.Vorotnikov et al.: 1987 Kiev, Vol.3, p.76 (1987). 9428 1451 357 18) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9428 1451 358 19) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9428 1451 359 Japanese. 9428 1451 360 20) C.Kalbach: Phys. Rev. C33, 818 (1986). 9428 1451 361 21) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9428 1451 362 22) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9428 1451 363 23) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9428 1451 364 24) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9428 1451 365 25) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9428 1451 366 26) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9428 1451 367 9428 1451 368 1 451 380 19428 1451 369 2 151 4 19428 1451 370 3 4 24 19428 1451 371 3 16 12 19428 1451 372 3 17 7 19428 1451 373 3 18 240 19428 1451 374 3 102 268 19428 1451 375 8 4 2 19428 1451 376 8 16 2 19428 1451 377 8 17 2 19428 1451 378 8 18 2 19428 1451 379 8 102 2 19428 1451 380 9428 1 099999 9428 0 0 0 9.423600+4 2.340180+2 0 0 1 09428 2151 1 9.423600+4 1.000000+0 0 0 1 09428 2151 2 1.000000-5 1.000000+1 0 0 0 09428 2151 3 0.000000+0 9.460000-1 0 0 0 09428 2151 4 9428 2 099999 9428 0 0 0 9.423600+4 2.340180+2 0 0 0 09428 3 4 1 0.000000+0-4.463000+4 0 0 1 619428 3 4 2 61 2 9428 3 4 3 4.482070+4 0.000000+0 5.000000+4 6.629060-3 7.000000+4 5.372330-29428 3 4 4 1.000000+5 1.427240-1 1.159850+5 1.847896-1 1.300000+5 2.216717-19428 3 4 5 1.480800+5 2.663782-1 1.700000+5 3.165424-1 2.000000+5 3.863027-19428 3 4 6 3.000000+5 5.420319-1 3.071070+5 5.478005-1 4.000000+5 6.202723-19428 3 4 7 5.000000+5 7.062966-1 5.179040+5 7.133705-1 6.000000+5 7.406938-19428 3 4 8 7.000000+5 7.740513-1 7.768050+5 7.782916-1 8.000000+5 7.783407-19428 3 4 9 9.000000+5 7.908618-1 1.000000+6 8.255758-1 1.300000+6 9.603679-19428 3 4 10 1.600000+6 1.091866+0 1.800000+6 1.155761+0 2.000000+6 1.198698+09428 3 4 11 2.300000+6 1.229808+0 2.500000+6 1.233741+0 2.700000+6 1.230560+09428 3 4 12 3.000000+6 1.258776+0 3.500000+6 1.268529+0 4.000000+6 1.315005+09428 3 4 13 4.500000+6 1.376867+0 5.000000+6 1.418959+0 5.500000+6 1.373382+09428 3 4 14 6.000000+6 1.224885+0 6.500000+6 1.031472+0 7.000000+6 8.749336-19428 3 4 15 7.500000+6 7.599834-1 8.000000+6 6.799932-1 8.500000+6 6.193597-19428 3 4 16 9.000000+6 5.748642-1 9.500000+6 5.386595-1 1.000000+7 5.096962-19428 3 4 17 1.050000+7 4.851397-1 1.100000+7 4.636091-1 1.150000+7 4.446171-19428 3 4 18 1.200000+7 4.270919-1 1.250000+7 4.110637-1 1.300000+7 3.956221-19428 3 4 19 1.350000+7 3.815258-1 1.400000+7 3.679487-1 1.450000+7 3.553960-19428 3 4 20 1.500000+7 3.430514-1 1.550000+7 3.320076-1 1.600000+7 3.210364-19428 3 4 21 1.650000+7 3.112780-1 1.700000+7 3.016033-1 1.750000+7 2.930352-19428 3 4 22 1.800000+7 2.846049-1 1.850000+7 2.769840-1 1.950000+7 2.629515-19428 3 4 23 2.000000+7 2.563440-1 9428 3 4 24 9428 3 099999 9.423600+4 2.340180+2 0 0 0 09428 3 16 1 -7.352280+6-7.352280+6 0 0 1 259428 3 16 2 25 2 9428 3 16 3 7.383700+6 0.000000+0 8.000000+6 3.489500-3 8.500000+6 1.662950-29428 3 16 4 9.000000+6 3.008380-2 9.500000+6 5.005100-2 1.000000+7 6.360400-29428 3 16 5 1.050000+7 7.415670-2 1.100000+7 9.122190-2 1.150000+7 1.093000-19428 3 16 6 1.200000+7 1.327410-1 1.250000+7 1.572810-1 1.300000+7 1.828670-19428 3 16 7 1.350000+7 2.063790-1 1.400000+7 2.189260-1 1.450000+7 2.167730-19428 3 16 8 1.500000+7 2.027340-1 1.550000+7 1.820390-1 1.600000+7 1.583410-19428 3 16 9 1.650000+7 1.369470-1 1.700000+7 1.180890-1 1.750000+7 1.015750-19428 3 16 10 1.800000+7 8.928900-2 1.850000+7 7.861810-2 1.950000+7 6.466860-29428 3 16 11 2.000000+7 6.051340-2 9428 3 16 12 9428 3 099999 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