JENDL-5 (Neutron sublibrary (activation cs)) Es-255 0 0 0 0 9.925500+4 2.528990+2 0 0 6 19916 1451 1 0.000000+0 1.000000+0 0 0 0 69916 1451 2 1.000000+0 2.000000+7 0 0 10 59916 1451 3 2.936000+2 0.000000+0 4 0 308 149916 1451 4 99-Es-255 JAEA+ EVAL-DEC07 O.Iwamoto, T.Nakagawa, et al. 9916 1451 5 DIST-DEC21 20100304 9916 1451 6 ----JENDL-5 MATERIAL 9916 9916 1451 7 -----INCIDENT NEUTRON DATA 9916 1451 8 ------ENDF-6 FORMAT 9916 1451 9 9916 1451 10 History 9916 1451 11 07-09 Theoretical calculation was performed with CCONE code. 9916 1451 12 07-10 Re-calculation was made with CCONE code. 9916 1451 13 07-12 Data were compiled as JENDL/AC-2008/1/. 9916 1451 14 10-02 Data of prompt gamma rays due to fission were given. 9916 1451 15 10-03 Covariance data were given. 9916 1451 16 9916 1451 17 21-11 revised by O.Iwamoto 9916 1451 18 (MF3/MT19-21,38) deleted 9916 1451 19 (MF8/MT4,16-18,37,102) added 9916 1451 20 9916 1451 21 MF=1 General information 9916 1451 22 MT=452 Number of Neutrons per fission 9916 1451 23 Sum of MT's=455 and 456. 9916 1451 24 9916 1451 25 MT=455 Delayed neutron data 9916 1451 26 (Same as JENDL-3.3) 9916 1451 27 Estimated from systematics by Tuttle/2/, Benedetti et al./3/ 9916 1451 28 and Waldo et al./4/ 9916 1451 29 9916 1451 30 MT=456 Number of prompt neutrons per fission 9916 1451 31 (Same as JENDL-3.3) 9916 1451 32 Estimated from Howerton's sytematics/5/. 9916 1451 33 9916 1451 34 9916 1451 35 MF= 2 Resonance parameters 9916 1451 36 MT=151 9916 1451 37 No resonance parameters are given. 9916 1451 38 9916 1451 39 9916 1451 40 Thermal cross sections and resonance integrals (at 300K) 9916 1451 41 ------------------------------------------------------- 9916 1451 42 0.0253 eV reson. integ.(*) 9916 1451 43 (barns) (barns) 9916 1451 44 ------------------------------------------------------- 9916 1451 45 total 64.90 9916 1451 46 elastic 9.32 9916 1451 47 fission 0.50 2.92 9916 1451 48 capture 55.00 1390 9916 1451 49 ------------------------------------------------------- 9916 1451 50 (*) In the energy range from 0.5 eV to 10 MeV. 9916 1451 51 9916 1451 52 9916 1451 53 MF= 3 Neutron cross sections 9916 1451 54 Below 0.25 eV: 9916 1451 55 * Elastic scattering cross section is 9.3 b calculated from 9916 1451 56 scattering radius of 8.594 fm/6/. 9916 1451 57 * Fission cross section is in the 1/v shape. CCONE calculation9916 1451 58 above 1.0 eV was extrapolated down to 1.0e-5 eV. 9916 1451 59 * Capture cross section is in the 1/v shape, and 55 b at 9916 1451 60 0.0253 eV which is an effective cross section measured by 9916 1451 61 Lougheed et al./7/ 9916 1451 62 9916 1451 63 Above 0.25 eV: 9916 1451 64 Cross sections were calculated with CCONE code/6/. 9916 1451 65 9916 1451 66 MT= 1 Total cross section 9916 1451 67 The cross section was calculated with CC OMP of Soukhovitskii 9916 1451 68 et al./8/ 9916 1451 69 9916 1451 70 9916 1451 71 MF= 4 Angular distributions of secondary neutrons 9916 1451 72 MT=2 Elastic scattering 9916 1451 73 Calculated with CCONE code/6/. 9916 1451 74 9916 1451 75 MT=18 Fission 9916 1451 76 Isotropic distributions in the laboratory system were assumed.9916 1451 77 9916 1451 78 9916 1451 79 MF= 5 Energy distributions of secondary neutrons 9916 1451 80 MT=18 Prompt netrons 9916 1451 81 Calculated with CCONE code/6/. 9916 1451 82 9916 1451 83 9916 1451 84 MF= 6 Energy-angle distributions 9916 1451 85 Calculated with CCONE code/6/. 9916 1451 86 Distributions from fission (MT=18) are not included. 9916 1451 87 9916 1451 88 9916 1451 89 MF=12 Photon production multiplicities 9916 1451 90 MT=18 Fission 9916 1451 91 Calculated from the total energy released by the prompt 9916 1451 92 gamma-rays due to fission which was estimated from its 9916 1451 93 systematics, and the average energy of gamma-rays. 9916 1451 94 9916 1451 95 9916 1451 96 MF=14 Photon angular distributions 9916 1451 97 MT=18 Fission 9916 1451 98 Isotoropic distributions were assumed. 9916 1451 99 9916 1451 100 9916 1451 101 MF=15 Continuous photon energy spectra 9916 1451 102 MT=18 Fission 9916 1451 103 Experimental data measured by Verbinski et al./9/ for 9916 1451 104 Pu-239 thermal fission were adopted. 9916 1451 105 9916 1451 106 9916 1451 107 MF=31 Covariances of average number of neutrons per fission 9916 1451 108 MT=452 Number of neutrons per fission 9916 1451 109 Sum of covariances for MT=455 and MT=456. 9916 1451 110 9916 1451 111 MT=455 9916 1451 112 Error of 15% was assumed. 9916 1451 113 9916 1451 114 MT=456 9916 1451 115 Covariance was obtained by fitting a linear function to the 9916 1451 116 at 0.0 and 5.0 MeV with an uncertainty of 10%. 9916 1451 117 9916 1451 118 9916 1451 119 MF=33 Covariances of neutron cross sections 9916 1451 120 Covariances were given to all the cross sections by using 9916 1451 121 KALMAN code/10/ and the covariances of model parameters 9916 1451 122 used in the cross-section calculations. 9916 1451 123 9916 1451 124 For the following cross sections, standard deviations in the 9916 1451 125 energy region below 0.1 eV were assumed as follows: 9916 1451 126 9916 1451 127 Total 43 % 9916 1451 128 Elastic scattering 50 % 9916 1451 129 Fission 50 % 9916 1451 130 Capture 50 % 9916 1451 131 9916 1451 132 9916 1451 133 MF=34 Covariances for Angular Distributions 9916 1451 134 MT=2 Elastic scattering 9916 1451 135 Covariances were given only to P1 components. 9916 1451 136 9916 1451 137 9916 1451 138 MF=35 Covariances for Energy Distributions 9916 1451 139 MT=18 Fission spectra 9916 1451 140 Estimated with CCONE and KALMAN codes. 9916 1451 141 9916 1451 142 9916 1451 143 ***************************************************************** 9916 1451 144 Calculation with CCONE code 9916 1451 145 ***************************************************************** 9916 1451 146 9916 1451 147 Models and parameters used in the CCONE/6/ calculation 9916 1451 148 1) Coupled channel optical model 9916 1451 149 Levels in the rotational band were included. Optical model 9916 1451 150 potential and coupled levels are shown in Table 1. 9916 1451 151 9916 1451 152 2) Two-component exciton model/11/ 9916 1451 153 * Global parametrization of Koning-Duijvestijn/12/ 9916 1451 154 was used. 9916 1451 155 * Gamma emission channel/13/ was added to simulate direct 9916 1451 156 and semi-direct capture reaction. 9916 1451 157 9916 1451 158 3) Hauser-Feshbach statistical model 9916 1451 159 * Moldauer width fluctuation correction/14/ was included. 9916 1451 160 * Neutron, gamma and fission decay channel were included. 9916 1451 161 * Transmission coefficients of neutrons were taken from 9916 1451 162 coupled channel calculation in Table 1. 9916 1451 163 * The level scheme of the target is shown in Table 2. 9916 1451 164 * Level density formula of constant temperature and Fermi-gas 9916 1451 165 model were used with shell energy correction and collective 9916 1451 166 enhancement factor. Parameters are shown in Table 3. 9916 1451 167 * Fission channel: 9916 1451 168 Double humped fission barriers were assumed. 9916 1451 169 Fission barrier penetrabilities were calculated with 9916 1451 170 Hill-Wheler formula/15/. Fission barrier parameters were 9916 1451 171 shown in Table 4. Transition state model was used and 9916 1451 172 continuum levels are assumed above the saddles. The level 9916 1451 173 density parameters for inner and outer saddles are shown in 9916 1451 174 Tables 5 and 6, respectively. 9916 1451 175 * Gamma-ray strength function of Kopecky et al/16/,/17/ 9916 1451 176 was used. The prameters are shown in Table 7. 9916 1451 177 9916 1451 178 9916 1451 179 ------------------------------------------------------------------9916 1451 180 Tables 9916 1451 181 ------------------------------------------------------------------9916 1451 182 9916 1451 183 Table 1. Coupled channel calculation 9916 1451 184 -------------------------------------------------- 9916 1451 185 * rigid rotor model was applied 9916 1451 186 * coupled levels = 0,1,2 (see Table 2) 9916 1451 187 * optical potential parameters /8/ 9916 1451 188 Volume: 9916 1451 189 V_0 = 49.97 MeV 9916 1451 190 lambda_HF = 0.01004 1/MeV 9916 1451 191 C_viso = 15.9 MeV 9916 1451 192 A_v = 12.04 MeV 9916 1451 193 B_v = 81.36 MeV 9916 1451 194 E_a = 385 MeV 9916 1451 195 r_v = 1.2568 fm 9916 1451 196 a_v = 0.633 fm 9916 1451 197 Surface: 9916 1451 198 W_0 = 17.2 MeV 9916 1451 199 B_s = 11.19 MeV 9916 1451 200 C_s = 0.01361 1/MeV 9916 1451 201 C_wiso = 23.5 MeV 9916 1451 202 r_s = 1.1803 fm 9916 1451 203 a_s = 0.601 fm 9916 1451 204 Spin-orbit: 9916 1451 205 V_so = 5.75 MeV 9916 1451 206 lambda_so = 0.005 1/MeV 9916 1451 207 W_so = -3.1 MeV 9916 1451 208 B_so = 160 MeV 9916 1451 209 r_so = 1.1214 fm 9916 1451 210 a_so = 0.59 fm 9916 1451 211 Coulomb: 9916 1451 212 C_coul = 1.3 9916 1451 213 r_c = 1.2452 fm 9916 1451 214 a_c = 0.545 fm 9916 1451 215 Deformation: 9916 1451 216 beta_2 = 0.213 9916 1451 217 beta_4 = 0.066 9916 1451 218 beta_6 = 0.0015 9916 1451 219 9916 1451 220 * Calculated strength function 9916 1451 221 S0= 1.24e-4 S1= 3.29e-4 R'= 8.59 fm (En=1 keV) 9916 1451 222 -------------------------------------------------- 9916 1451 223 9916 1451 224 Table 2. Level Scheme of Es-255 9916 1451 225 ------------------- 9916 1451 226 No. Ex(MeV) J PI 9916 1451 227 ------------------- 9916 1451 228 0 0.00000 7/2 + * 9916 1451 229 1 0.04640 9/2 + * 9916 1451 230 2 0.08000 11/2 + * 9916 1451 231 ------------------- 9916 1451 232 *) Coupled levels in CC calculation 9916 1451 233 9916 1451 234 Table 3. Level density parameters 9916 1451 235 -------------------------------------------------------- 9916 1451 236 Nuclide a* Pair Eshell T E0 Ematch 9916 1451 237 1/MeV MeV MeV MeV MeV MeV 9916 1451 238 -------------------------------------------------------- 9916 1451 239 Es-256 19.5580 0.0000 2.3378 0.2695 -0.6890 1.0000 9916 1451 240 Es-255 19.4922 0.7515 2.2159 0.3615 -0.7550 2.8069 9916 1451 241 Es-254 19.4263 0.0000 1.6001 0.2773 -0.6899 1.0000 9916 1451 242 Es-253 19.3604 0.7544 1.3654 0.3757 -0.7841 2.8632 9916 1451 243 Es-252 19.2945 0.0000 0.8872 0.2854 -0.6910 1.0000 9916 1451 244 -------------------------------------------------------- 9916 1451 245 9916 1451 246 Table 4. Fission barrier parameters 9916 1451 247 ---------------------------------------- 9916 1451 248 Nuclide V_A hw_A V_B hw_B 9916 1451 249 MeV MeV MeV MeV 9916 1451 250 ---------------------------------------- 9916 1451 251 Es-256 6.200 0.650 5.800 0.450 9916 1451 252 Es-255 6.120 0.800 4.800 0.520 9916 1451 253 Es-254 6.200 0.650 5.800 0.450 9916 1451 254 Es-253 6.200 0.800 5.400 0.520 9916 1451 255 Es-252 6.200 0.650 5.800 0.450 9916 1451 256 ---------------------------------------- 9916 1451 257 9916 1451 258 Table 5. Level density above inner saddle 9916 1451 259 -------------------------------------------------------- 9916 1451 260 Nuclide a* Pair Eshell T E0 Ematch 9916 1451 261 1/MeV MeV MeV MeV MeV MeV 9916 1451 262 -------------------------------------------------------- 9916 1451 263 Es-256 21.9050 0.0000 2.4000 0.3187 -2.4148 2.0000 9916 1451 264 Es-255 21.8312 0.8767 2.4000 0.3193 -1.5382 2.8767 9916 1451 265 Es-254 21.7575 0.0000 2.4000 0.3199 -2.4149 2.0000 9916 1451 266 Es-253 21.6837 0.8802 2.4000 0.3205 -1.5348 2.8802 9916 1451 267 Es-252 21.6098 0.0000 2.4000 0.3211 -2.4150 2.0000 9916 1451 268 -------------------------------------------------------- 9916 1451 269 9916 1451 270 Table 6. Level density above outer saddle 9916 1451 271 -------------------------------------------------------- 9916 1451 272 Nuclide a* Pair Eshell T E0 Ematch 9916 1451 273 1/MeV MeV MeV MeV MeV MeV 9916 1451 274 -------------------------------------------------------- 9916 1451 275 Es-256 21.9050 0.0000 1.1600 0.3438 -1.7132 2.0000 9916 1451 276 Es-255 21.8312 0.8767 1.1200 0.3449 -0.8359 2.8767 9916 1451 277 Es-254 21.7575 0.0000 1.0800 0.3459 -1.7120 2.0000 9916 1451 278 Es-253 21.6837 0.8802 1.0400 0.3470 -0.8313 2.8802 9916 1451 279 Es-252 21.6098 0.0000 1.0000 0.3481 -1.7109 2.0000 9916 1451 280 -------------------------------------------------------- 9916 1451 281 9916 1451 282 Table 7. Gamma-ray strength function for Es-256 9916 1451 283 -------------------------------------------------------- 9916 1451 284 K0 = 1.500 E0 = 4.500 (MeV) 9916 1451 285 * E1: ER = 11.36 (MeV) EG = 2.70 (MeV) SIG = 262.73 (mb) 9916 1451 286 ER = 14.15 (MeV) EG = 4.10 (MeV) SIG = 525.47 (mb) 9916 1451 287 * M1: ER = 6.46 (MeV) EG = 4.00 (MeV) SIG = 1.89 (mb) 9916 1451 288 * E2: ER = 9.92 (MeV) EG = 3.04 (MeV) SIG = 7.50 (mb) 9916 1451 289 -------------------------------------------------------- 9916 1451 290 9916 1451 291 9916 1451 292 References 9916 1451 293 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9916 1451 294 2) R.J.Tuttld: INDC(NDS)-107/G+Special, p.29 (1979). 9916 1451 295 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 9916 1451 296 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 9916 1451 297 5) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9916 1451 298 6) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9916 1451 299 7) R.W.Lougheed et al.: J. Inorg. Nucl. Chem., 43, 2239 (1981). 9916 1451 300 8) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9916 1451 301 9) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9916 1451 302 10) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9916 1451 303 Japanese. 9916 1451 304 11) C.Kalbach: Phys. Rev. C33, 818 (1986). 9916 1451 305 12) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9916 1451 306 13) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9916 1451 307 14) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9916 1451 308 15) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9916 1451 309 16) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9916 1451 310 17) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9916 1451 311 9916 1451 312 1 451 326 19916 1451 313 2 151 4 19916 1451 314 3 4 26 19916 1451 315 3 16 13 19916 1451 316 3 17 10 19916 1451 317 3 18 140 19916 1451 318 3 37 5 19916 1451 319 3 102 176 19916 1451 320 8 4 2 19916 1451 321 8 16 2 19916 1451 322 8 17 2 19916 1451 323 8 18 2 19916 1451 324 8 37 2 19916 1451 325 8 102 2 19916 1451 326 9916 1 099999 9916 0 0 0 9.925500+4 2.528990+2 0 0 1 09916 2151 1 9.925500+4 1.000000+0 0 0 1 09916 2151 2 1.000000-5 2.500000-1 0 0 0 09916 2151 3 3.500000+0 8.594000-1 0 0 0 09916 2151 4 9916 2 099999 9916 0 0 0 9.925500+4 2.528990+2 0 0 0 09916 3 4 1 0.000000+0-4.640000+4 0 0 1 689916 3 4 2 68 2 9916 3 4 3 4.658350+4 0.000000+0 5.000000+4 1.151900-1 7.000000+4 3.424150-19916 3 4 4 8.031630+4 4.326260-1 1.000000+5 6.377361-1 1.108720+5 7.276491-19916 3 4 5 1.200000+5 8.031842-1 1.400000+5 9.378584-1 1.700000+5 1.099118+09916 3 4 6 2.000000+5 1.528921+0 2.500000+5 1.654209+0 3.000000+5 2.245073+09916 3 4 7 4.000000+5 2.679101+0 5.000000+5 3.028559+0 6.000000+5 3.192298+09916 3 4 8 7.000000+5 3.313723+0 8.000000+5 3.364115+0 9.000000+5 3.364350+09916 3 4 9 1.000000+6 3.324659+0 1.100000+6 3.257375+0 1.200000+6 3.185751+09916 3 4 10 1.300000+6 3.126063+0 1.400000+6 3.090157+0 1.500000+6 3.057327+09916 3 4 11 1.600000+6 3.034732+0 1.700000+6 3.003346+0 1.800000+6 2.974566+09916 3 4 12 1.900000+6 2.937838+0 2.000000+6 2.901101+0 2.100000+6 2.861350+09916 3 4 13 2.300000+6 2.780414+0 2.500000+6 2.703759+0 2.700000+6 2.632632+09916 3 4 14 3.000000+6 2.534431+0 3.500000+6 2.436130+0 4.000000+6 2.348910+09916 3 4 15 4.500000+6 2.322556+0 5.000000+6 2.304199+0 5.500000+6 2.291438+09916 3 4 16 6.000000+6 2.125843+0 6.500000+6 1.649252+0 7.000000+6 1.204443+09916 3 4 17 7.500000+6 8.912098-1 8.000000+6 7.001033-1 8.500000+6 5.840265-19916 3 4 18 9.000000+6 5.152777-1 9.500000+6 4.703807-1 1.000000+7 4.394048-19916 3 4 19 1.050000+7 4.155060-1 1.100000+7 3.953361-1 1.150000+7 3.787831-19916 3 4 20 1.200000+7 3.628612-1 1.250000+7 3.483506-1 1.300000+7 3.341270-19916 3 4 21 1.350000+7 3.208417-1 1.400000+7 3.085104-1 1.450000+7 2.965264-19916 3 4 22 1.500000+7 2.853823-1 1.550000+7 2.743245-1 1.600000+7 2.647011-19916 3 4 23 1.650000+7 2.557288-1 1.700000+7 2.469925-1 1.750000+7 2.390960-19916 3 4 24 1.800000+7 2.312834-1 1.850000+7 2.241913-1 1.900000+7 2.171062-19916 3 4 25 1.950000+7 2.118429-1 2.000000+7 2.055401-1 9916 3 4 26 9916 3 099999 9.925500+4 2.528990+2 0 0 0 09916 3 16 1 -5.974430+6-5.974430+6 0 0 1 299916 3 16 2 29 2 9916 3 16 3 5.998050+6 0.000000+0 6.500000+6 4.190720-2 7.000000+6 2.117110-19916 3 16 4 7.500000+6 4.441020-1 8.000000+6 6.615270-1 8.500000+6 8.190690-19916 3 16 5 9.000000+6 9.190980-1 9.500000+6 9.635460-1 1.000000+7 9.766960-19916 3 16 6 1.050000+7 9.683380-1 1.100000+7 9.557750-1 1.150000+7 9.384320-19916 3 16 7 1.200000+7 9.084750-1 1.250000+7 8.366160-1 1.300000+7 7.252370-19916 3 16 8 1.350000+7 6.161170-1 1.400000+7 5.116910-1 1.450000+7 4.186980-19916 3 16 9 1.500000+7 3.576180-1 1.550000+7 2.988070-1 1.600000+7 2.618410-19916 3 16 10 1.650000+7 2.369560-1 1.700000+7 2.158140-1 1.750000+7 1.996680-19916 3 16 11 1.800000+7 1.868880-1 1.850000+7 1.796520-1 1.900000+7 1.705490-19916 3 16 12 1.950000+7 1.626260-1 2.000000+7 1.554610-1 9916 3 16 13 9916 3 099999 9.925500+4 2.528990+2 0 0 0 09916 3 17 1 -1.106750+7-1.106750+7 0 0 1 199916 3 17 2 19 2 9916 3 17 3 1.111120+7 0.000000+0 1.150000+7 7.026170-4 1.200000+7 1.900510-29916 3 17 4 1.250000+7 7.544500-2 1.300000+7 1.579680-1 1.350000+7 2.283440-19916 3 17 5 1.400000+7 2.863100-1 1.450000+7 3.298050-1 1.500000+7 3.434900-19916 3 17 6 1.550000+7 3.636120-1 1.600000+7 3.648940-1 1.650000+7 3.648950-19916 3 17 7 1.700000+7 3.637170-1 1.750000+7 3.625260-1 1.800000+7 3.593670-19916 3 17 8 1.850000+7 3.479770-1 1.900000+7 3.366170-1 1.950000+7 3.154880-19916 3 17 9 2.000000+7 2.946090-1 9916 3 17 10 9916 3 099999 9.925500+4 2.528990+2 0 0 0 09916 3 18 1 2.213000+8 2.213000+8 0 0 1 4099916 3 18 2 409 2 9916 3 18 3 1.000000-5 2.573486+1 1.103037-5 2.450276+1 1.216691-5 2.332958+19916 3 18 4 1.342055-5 2.221250+1 1.480336-5 2.114885+1 1.632865-5 2.013606+19916 3 18 5 1.801111-5 1.917170+1 1.986691-5 1.825344+1 2.191394-5 1.737909+19916 3 18 6 2.417189-5 1.654654+1 2.666248-5 1.575379+1 2.940971-5 1.499893+19916 3 18 7 3.243999-5 1.428015+1 3.578251-5 1.359573+1 3.946943-5 1.294402+19916 3 18 8 4.353624-5 1.232345+1 4.802208-5 1.173253+1 5.297013-5 1.116985+19916 3 18 9 5.842801-5 1.063406+1 6.444825-5 1.012387+1 7.108881-5 9.638048+09916 3 18 10 7.841358-5 9.175442+0 8.649308-5 8.734940+0 9.540506-5 8.315487+09916 3 18 11 1.052353-4 7.916077+0 1.160784-4 7.535757+0 1.280388-4 7.173615+09916 3 18 12 1.412315-4 6.828788+0 1.557836-4 6.500450+0 1.718351-4 6.187818+09916 3 18 13 1.895404-4 5.890146+0 2.090701-4 5.606722+0 2.306120-4 5.336872+09916 3 18 14 2.543736-4 5.079949+0 2.805835-4 4.835342+0 3.094939-4 4.602466+09916 3 18 15 3.413832-4 4.380763+0 3.765583-4 4.169703+0 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