JENDL-5 (Neutron sublibrary (activation cs)) Pa-230 0 0 0 0 9.123000+4 2.280580+2 0 0 6 19128 1451 1 0.000000+0 1.000000+0 0 0 0 69128 1451 2 1.000000+0 2.000000+7 0 0 10 59128 1451 3 2.936000+2 0.000000+0 4 0 314 149128 1451 4 91-Pa-230 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9128 1451 5 DIST-DEC21 20100304 9128 1451 6 ----JENDL-5 MATERIAL 9128 9128 1451 7 -----INCIDENT NEUTRON DATA 9128 1451 8 ------ENDF-6 FORMAT 9128 1451 9 9128 1451 10 History 9128 1451 11 07-10 Theoretical calculation was performed with CCONE code. 9128 1451 12 Data were compiled as JENDL/AC-2008/1/. 9128 1451 13 10-02 Data of prompt gamma rays due to fission were given. 9128 1451 14 10-03 Covariance data were given. 9128 1451 15 21-11 revised by O.Iwamoto 9128 1451 16 (MF3/MT19-21,38) deleted 9128 1451 17 (MF8/MT4,16-18,37,102) added 9128 1451 18 9128 1451 19 9128 1451 20 MF=1 General information 9128 1451 21 MT=452 Number of Neutrons per fission 9128 1451 22 Sum of MT's=455 and 456. 9128 1451 23 9128 1451 24 MT=455 Delayed neutron data 9128 1451 25 Estimated from systematics by Tuttle/2/, Benedetti et al./3/ 9128 1451 26 and Waldo et al./4/ 9128 1451 27 9128 1451 28 MT=456 Number of prompt neutrons per fission 9128 1451 29 Estimated from Howerton's systematics/5/. 9128 1451 30 9128 1451 31 9128 1451 32 MF= 2 Resonance parameters 9128 1451 33 MT=151 9128 1451 34 No resonance parameters are given. 9128 1451 35 9128 1451 36 9128 1451 37 Thermal cross sections and resonance integrals (at 300K) 9128 1451 38 ------------------------------------------------------- 9128 1451 39 0.0253 eV reson. integ.(*) 9128 1451 40 (barns) (barns) 9128 1451 41 ------------------------------------------------------- 9128 1451 42 total 1892.7 9128 1451 43 elastic 12.03 9128 1451 44 fission 1500.3 934 9128 1451 45 capture 380.1 235 9128 1451 46 ------------------------------------------------------- 9128 1451 47 (*) In the energy range from 0.5 eV to 10 MeV. 9128 1451 48 9128 1451 49 9128 1451 50 MF= 3 Neutron cross sections 9128 1451 51 Below 0.1 eV: 9128 1451 52 * Elastic scattering cross section is 12.0 b calculated from 9128 1451 53 scattering radius of 9.755 fm/6/. 9128 1451 54 * Fission cross section is in the 1/v shape. 9128 1451 55 1500 b at 0.0253 eV /7/ was adopted. 9128 1451 56 * Capture cross section is in the 1/v shape. 9128 1451 57 Cross section of 380 b at 0.0253 eV was estimated from 9128 1451 58 capture to fission ratio calculated at 1 eV with CCONE 9128 1451 59 code and fission cross section of 1500 b. 9128 1451 60 9128 1451 61 Above 0.1 eV: 9128 1451 62 Cross sections calculated with CCONE code/6/ were adopted. 9128 1451 63 9128 1451 64 MT= 1 Total cross section 9128 1451 65 The cross section was calculated with CC OMP of Soukhovitskii 9128 1451 66 et al./8/. 9128 1451 67 9128 1451 68 MT=18 Fission cross section 9128 1451 69 The simulated (n,f) cross sections measured by Britt and 9128 1451 70 Wilhelmy/9/ were used to determine the parameters in the 9128 1451 71 CCONE calculation. 9128 1451 72 9128 1451 73 9128 1451 74 MF= 4 Angular distributions of secondary neutrons 9128 1451 75 MT=2 Elastic scattering 9128 1451 76 Calculated with CCONE code/6/. 9128 1451 77 9128 1451 78 MT=18 Fission 9128 1451 79 Isotropic distributions in the laboratory system were assumed.9128 1451 80 9128 1451 81 9128 1451 82 MF= 5 Energy distributions of secondary neutrons 9128 1451 83 MT=18 Prompt neutrons 9128 1451 84 Calculated with CCONE code/6/. 9128 1451 85 9128 1451 86 9128 1451 87 MF= 6 Energy-angle distributions 9128 1451 88 Calculated with CCONE code/6/. 9128 1451 89 Distributions from fission (MT=18) are not included. 9128 1451 90 9128 1451 91 9128 1451 92 MF=12 Photon production multiplicities 9128 1451 93 MT=18 Fission 9128 1451 94 Calculated from the total energy released by the prompt 9128 1451 95 gamma-rays due to fission which was estimated from its 9128 1451 96 systematics, and the average energy of gamma-rays. 9128 1451 97 9128 1451 98 9128 1451 99 MF=14 Photon angular distributions 9128 1451 100 MT=18 Fission 9128 1451 101 Isotoropic distributions were assumed. 9128 1451 102 9128 1451 103 9128 1451 104 MF=15 Continuous photon energy spectra 9128 1451 105 MT=18 Fission 9128 1451 106 Experimental data measured by Verbinski et al./10/ for 9128 1451 107 U-235 thermal fission were adopted. 9128 1451 108 9128 1451 109 9128 1451 110 MF=31 Covariances of average number of neutrons per fission 9128 1451 111 MT=452 Number of neutrons per fission 9128 1451 112 Sum of covariances for MT=455 and MT=456. 9128 1451 113 9128 1451 114 MT=455 9128 1451 115 Error of 15% was assumed. 9128 1451 116 9128 1451 117 MT=456 9128 1451 118 Covariance was obtained by fitting a linear function to the 9128 1451 119 at 0.0 and 5.0 MeV with an uncertainty of 5%. 9128 1451 120 9128 1451 121 9128 1451 122 MF=33 Covariances of neutron cross sections 9128 1451 123 Covariances were given to all the cross sections by using 9128 1451 124 KALMAN code/11/ and the covariances of model parameters 9128 1451 125 used in the cross-section calculations. 9128 1451 126 9128 1451 127 Covariances of the fission cross section were determined from 9128 1451 128 experimental data. 9128 1451 129 9128 1451 130 For the following cross sections, standard deviations in the 9128 1451 131 energy region below 0.1 eV were assumed as follows: 9128 1451 132 9128 1451 133 Total 74 % 9128 1451 134 Elastic scattering 90 % 9128 1451 135 Fission 90 % 9128 1451 136 Capture 90 % 9128 1451 137 9128 1451 138 9128 1451 139 MF=34 Covariances for Angular Distributions 9128 1451 140 MT=2 Elastic scattering 9128 1451 141 Covariances were given only to P1 components. 9128 1451 142 9128 1451 143 9128 1451 144 MF=35 Covariances for Energy Distributions 9128 1451 145 MT=18 Fission spectra 9128 1451 146 Estimated with CCONE and KALMAN codes. 9128 1451 147 9128 1451 148 9128 1451 149 ***************************************************************** 9128 1451 150 Calculation with CCONE code 9128 1451 151 ***************************************************************** 9128 1451 152 9128 1451 153 Models and parameters used in the CCONE/6/ calculation 9128 1451 154 1) Coupled channel optical model 9128 1451 155 Levels in the rotational band were included. Optical model 9128 1451 156 potential and coupled levels are shown in Table 1. 9128 1451 157 9128 1451 158 2) Two-component exciton model/12/ 9128 1451 159 * Global parametrization of Koning-Duijvestijn/13/ 9128 1451 160 was used. 9128 1451 161 * Gamma emission channel/14/ was added to simulate direct 9128 1451 162 and semi-direct capture reaction. 9128 1451 163 9128 1451 164 3) Hauser-Feshbach statistical model 9128 1451 165 * Moldauer width fluctuation correction/15/ was included. 9128 1451 166 * Neutron, gamma and fission decay channel were included. 9128 1451 167 * Transmission coefficients of neutrons were taken from 9128 1451 168 coupled channel calculation in Table 1. 9128 1451 169 * The level scheme of the target is shown in Table 2. 9128 1451 170 * Level density formula of constant temperature and Fermi-gas 9128 1451 171 model were used with shell energy correction and collective 9128 1451 172 enhancement factor. Parameters are shown in Table 3. 9128 1451 173 * Fission channel: 9128 1451 174 Double humped fission barriers were assumed. 9128 1451 175 Fission barrier penetrabilities were calculated with 9128 1451 176 Hill-Wheler formula/16/. Fission barrier parameters were 9128 1451 177 shown in Table 4. Transition state model was used and 9128 1451 178 continuum levels are assumed above the saddles. The level 9128 1451 179 density parameters for inner and outer saddles are shown in 9128 1451 180 Tables 5 and 6, respectively. 9128 1451 181 * Gamma-ray strength function of Kopecky et al/17/,/18/ 9128 1451 182 was used. The prameters are shown in Table 7. 9128 1451 183 9128 1451 184 9128 1451 185 ------------------------------------------------------------------9128 1451 186 Tables 9128 1451 187 ------------------------------------------------------------------9128 1451 188 9128 1451 189 Table 1. Coupled channel calculation 9128 1451 190 -------------------------------------------------- 9128 1451 191 * rigid rotor model was applied 9128 1451 192 * coupled levels = 0,1,2,3 (see Table 2) 9128 1451 193 * optical potential parameters /8/ 9128 1451 194 Volume: 9128 1451 195 V_0 = 49.97 MeV 9128 1451 196 lambda_HF = 0.01004 1/MeV 9128 1451 197 C_viso = 15.9 MeV 9128 1451 198 A_v = 12.04 MeV 9128 1451 199 B_v = 81.36 MeV 9128 1451 200 E_a = 385 MeV 9128 1451 201 r_v = 1.2568 fm 9128 1451 202 a_v = 0.633 fm 9128 1451 203 Surface: 9128 1451 204 W_0 = 17.2 MeV 9128 1451 205 B_s = 11.19 MeV 9128 1451 206 C_s = 0.01361 1/MeV 9128 1451 207 C_wiso = 23.5 MeV 9128 1451 208 r_s = 1.1803 fm 9128 1451 209 a_s = 0.601 fm 9128 1451 210 Spin-orbit: 9128 1451 211 V_so = 5.75 MeV 9128 1451 212 lambda_so = 0.005 1/MeV 9128 1451 213 W_so = -3.1 MeV 9128 1451 214 B_so = 160 MeV 9128 1451 215 r_so = 1.1214 fm 9128 1451 216 a_so = 0.59 fm 9128 1451 217 Coulomb: 9128 1451 218 C_coul = 1.3 9128 1451 219 r_c = 1.2452 fm 9128 1451 220 a_c = 0.545 fm 9128 1451 221 Deformation: 9128 1451 222 beta_2 = 0.213 9128 1451 223 beta_4 = 0.066 9128 1451 224 beta_6 = 0.0015 9128 1451 225 9128 1451 226 * Calculated strength function 9128 1451 227 S0= 0.99e-4 S1= 1.93e-4 R'= 9.76 fm (En=1 keV) 9128 1451 228 -------------------------------------------------- 9128 1451 229 9128 1451 230 Table 2. Level Scheme of Pa-230 9128 1451 231 ------------------- 9128 1451 232 No. Ex(MeV) J PI 9128 1451 233 ------------------- 9128 1451 234 0 0.00000 2 - * 9128 1451 235 1 0.06000 3 - * 9128 1451 236 ------------------- 9128 1451 237 *) Coupled levels in CC calculation 9128 1451 238 9128 1451 239 Table 3. Level density parameters 9128 1451 240 -------------------------------------------------------- 9128 1451 241 Nuclide a* Pair Eshell T E0 Ematch 9128 1451 242 1/MeV MeV MeV MeV MeV MeV 9128 1451 243 -------------------------------------------------------- 9128 1451 244 Pa-231 17.9034 0.7895 3.1164 0.4176 -1.2470 3.5007 9128 1451 245 Pa-230 17.8368 0.0000 2.9470 0.2794 -0.6728 1.0000 9128 1451 246 Pa-229 17.7702 0.7930 3.0707 0.3881 -0.8689 3.0597 9128 1451 247 Pa-228 17.7035 0.0000 2.9095 0.2810 -0.6716 1.0000 9128 1451 248 Pa-227 17.6369 0.7965 2.9512 0.3860 -0.8068 2.9965 9128 1451 249 -------------------------------------------------------- 9128 1451 250 9128 1451 251 Table 4. Fission barrier parameters 9128 1451 252 ---------------------------------------- 9128 1451 253 Nuclide V_A hw_A V_B hw_B 9128 1451 254 MeV MeV MeV MeV 9128 1451 255 ---------------------------------------- 9128 1451 256 Pa-231 6.000 0.800 5.850 0.520 9128 1451 257 Pa-230 5.800 0.800 6.180 0.400 9128 1451 258 Pa-229 6.000 0.800 5.800 0.520 9128 1451 259 Pa-228 5.800 0.800 6.180 0.400 9128 1451 260 Pa-227 6.000 0.800 5.800 0.520 9128 1451 261 ---------------------------------------- 9128 1451 262 9128 1451 263 Table 5. Level density above inner saddle 9128 1451 264 -------------------------------------------------------- 9128 1451 265 Nuclide a* Pair Eshell T E0 Ematch 9128 1451 266 1/MeV MeV MeV MeV MeV MeV 9128 1451 267 -------------------------------------------------------- 9128 1451 268 Pa-231 20.5889 0.9211 2.6000 0.3276 -1.4734 2.9211 9128 1451 269 Pa-230 20.5123 0.0000 2.6000 0.3428 -2.6080 2.2000 9128 1451 270 Pa-229 20.4357 0.9251 2.6000 0.3435 -1.6829 3.1251 9128 1451 271 Pa-228 20.3591 0.0000 2.6000 0.3442 -2.6080 2.2000 9128 1451 272 Pa-227 20.2824 0.9292 2.6000 0.3449 -1.6787 3.1292 9128 1451 273 -------------------------------------------------------- 9128 1451 274 9128 1451 275 Table 6. Level density above outer saddle 9128 1451 276 -------------------------------------------------------- 9128 1451 277 Nuclide a* Pair Eshell T E0 Ematch 9128 1451 278 1/MeV MeV MeV MeV MeV MeV 9128 1451 279 -------------------------------------------------------- 9128 1451 280 Pa-231 22.3792 0.9211 -0.1200 0.3380 -0.5880 2.7211 9128 1451 281 Pa-230 20.5123 0.0000 -0.1600 0.3867 -1.8562 2.2000 9128 1451 282 Pa-229 20.4357 0.9251 -0.2000 0.3880 -0.9302 3.1251 9128 1451 283 Pa-228 20.3591 0.0000 -0.2400 0.3894 -1.8544 2.2000 9128 1451 284 Pa-227 20.2824 0.9292 -0.2800 0.3908 -0.9243 3.1292 9128 1451 285 -------------------------------------------------------- 9128 1451 286 9128 1451 287 Table 7. Gamma-ray strength function for Pa-231 9128 1451 288 -------------------------------------------------------- 9128 1451 289 K0 = 1.502 E0 = 4.500 (MeV) 9128 1451 290 * E1: ER = 11.03 (MeV) EG = 2.71 (MeV) SIG = 302.00 (mb) 9128 1451 291 ER = 13.87 (MeV) EG = 4.77 (MeV) SIG = 449.00 (mb) 9128 1451 292 * M1: ER = 6.68 (MeV) EG = 4.00 (MeV) SIG = 2.80 (mb) 9128 1451 293 * E2: ER = 10.27 (MeV) EG = 3.34 (MeV) SIG = 6.39 (mb) 9128 1451 294 -------------------------------------------------------- 9128 1451 295 9128 1451 296 9128 1451 297 References 9128 1451 298 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9128 1451 299 2) R.J.Tuttle: INDC(NDS)-107/G+Special, p.29 (1979). 9128 1451 300 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 9128 1451 301 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 9128 1451 302 5) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9128 1451 303 6) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9128 1451 304 7) Ghiorso et al.: comment given in CINDA (1954). 9128 1451 305 8) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9128 1451 306 9) H.C.Britt, J.B.Wilhelmy: Nucl. Sci. Eng., 72, 222 (1979). 9128 1451 307 10) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9128 1451 308 11) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9128 1451 309 Japanese. 9128 1451 310 12) C.Kalbach: Phys. Rev. C33, 818 (1986). 9128 1451 311 13) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9128 1451 312 14) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9128 1451 313 15) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9128 1451 314 16) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9128 1451 315 17) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9128 1451 316 18) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9128 1451 317 9128 1451 318 1 451 332 19128 1451 319 2 151 4 19128 1451 320 3 4 25 19128 1451 321 3 16 13 19128 1451 322 3 17 8 19128 1451 323 3 18 116 19128 1451 324 3 37 4 19128 1451 325 3 102 142 19128 1451 326 8 4 2 19128 1451 327 8 16 2 19128 1451 328 8 17 2 19128 1451 329 8 18 2 19128 1451 330 8 37 2 19128 1451 331 8 102 2 19128 1451 332 9128 1 099999 9128 0 0 0 9.123000+4 2.280580+2 0 0 1 09128 2151 1 9.123000+4 1.000000+0 0 0 1 09128 2151 2 1.000000-5 1.000000-1 0 0 0 09128 2151 3 2.000000+0 9.755000-1 0 0 0 09128 2151 4 9128 2 099999 9128 0 0 0 9.123000+4 2.280580+2 0 0 0 09128 3 4 1 0.000000+0-6.000000+4 0 0 1 659128 3 4 2 65 2 9128 3 4 3 6.026310+4 0.000000+0 7.000000+4 9.082770-3 1.000000+5 2.600500-29128 3 4 4 1.109670+5 3.229984-2 1.200000+5 3.748497-2 1.400000+5 4.891945-29128 3 4 5 1.700000+5 1.008106-1 2.000000+5 1.198565-1 2.500000+5 1.400345-19128 3 4 6 3.000000+5 2.495040-1 4.000000+5 3.688070-1 5.000000+5 5.153620-19128 3 4 7 6.000000+5 6.300020-1 7.000000+5 7.558610-1 8.000000+5 8.596230-19128 3 4 8 9.000000+5 9.641140-1 1.000000+6 1.074155+0 1.100000+6 1.172985+09128 3 4 9 1.200000+6 1.268472+0 1.300000+6 1.360498+0 1.400000+6 1.446268+09128 3 4 10 1.500000+6 1.526478+0 1.600000+6 1.599296+0 1.700000+6 1.664043+09128 3 4 11 1.800000+6 1.721792+0 1.900000+6 1.771047+0 2.000000+6 1.814692+09128 3 4 12 2.300000+6 1.909112+0 2.500000+6 1.948378+0 2.700000+6 1.975861+09128 3 4 13 3.000000+6 2.000236+0 3.500000+6 2.011866+0 4.000000+6 2.008603+09128 3 4 14 4.500000+6 1.987113+0 5.000000+6 1.972674+0 5.500000+6 1.947289+09128 3 4 15 6.000000+6 1.932226+0 6.500000+6 1.760278+0 7.000000+6 1.442120+09128 3 4 16 7.500000+6 1.142000+0 8.000000+6 9.167960-1 8.500000+6 7.532960-19128 3 4 17 9.000000+6 6.414710-1 9.500000+6 5.620230-1 1.000000+7 5.060920-19128 3 4 18 1.050000+7 4.643470-1 1.100000+7 4.324680-1 1.150000+7 4.081010-19128 3 4 19 1.200000+7 3.878550-1 1.250000+7 3.707270-1 1.300000+7 3.554564-19128 3 4 20 1.350000+7 3.415997-1 1.400000+7 3.285670-1 1.450000+7 3.175463-19128 3 4 21 1.500000+7 3.059715-1 1.550000+7 2.959536-1 1.600000+7 2.862018-19128 3 4 22 1.650000+7 2.771358-1 1.700000+7 2.682298-1 1.750000+7 2.599387-19128 3 4 23 1.800000+7 2.518297-1 1.850000+7 2.442532-1 1.900000+7 2.369217-19128 3 4 24 1.950000+7 2.300613-1 2.000000+7 2.232268-1 9128 3 4 25 9128 3 099999 9.123000+4 2.280580+2 0 0 0 09128 3 16 1 -5.794780+6-5.794780+6 0 0 1 309128 3 16 2 30 2 9128 3 16 3 5.820190+6 0.000000+0 6.000000+6 3.997690-3 6.500000+6 9.889040-29128 3 16 4 7.000000+6 2.119480-1 7.500000+6 3.122400-1 8.000000+6 3.982020-19128 3 16 5 8.500000+6 4.657070-1 9.000000+6 5.184760-1 9.500000+6 5.588990-19128 3 16 6 1.000000+7 5.949080-1 1.050000+7 6.284390-1 1.100000+7 6.627670-19128 3 16 7 1.150000+7 6.926250-1 1.200000+7 7.191960-1 1.250000+7 7.299240-19128 3 16 8 1.300000+7 7.123880-1 1.350000+7 6.720710-1 1.400000+7 6.171380-19128 3 16 9 1.450000+7 5.548040-1 1.500000+7 4.972790-1 1.550000+7 4.428390-19128 3 16 10 1.600000+7 3.957000-1 1.650000+7 3.559540-1 1.700000+7 3.231580-19128 3 16 11 1.750000+7 2.965630-1 1.800000+7 2.748830-1 1.850000+7 2.573860-19128 3 16 12 1.900000+7 2.430830-1 1.950000+7 2.314040-1 2.000000+7 2.217000-19128 3 16 13 9128 3 099999 9.123000+4 2.280580+2 0 0 0 09128 3 17 1 -1.289230+7-1.289230+7 0 0 1 159128 3 17 2 15 2 9128 3 17 3 1.294880+7 0.000000+0 1.350000+7 2.740200-5 1.400000+7 6.285520-49128 3 17 4 1.450000+7 3.602450-3 1.500000+7 1.150430-2 1.550000+7 2.621690-29128 3 17 5 1.600000+7 4.448370-2 1.650000+7 7.159240-2 1.700000+7 9.866970-29128 3 17 6 1.750000+7 1.274660-1 1.800000+7 1.563540-1 1.850000+7 1.842990-19128 3 17 7 1.900000+7 2.105640-1 1.950000+7 2.349360-1 2.000000+7 2.569900-19128 3 17 8 9128 3 099999 9.123000+4 2.280580+2 0 0 0 09128 3 18 1 1.867500+8 1.867500+8 0 0 1 3399128 3 18 2 339 2 9128 3 18 3 1.000000-5 7.514423+4 1.103037-5 7.154883+4 1.216691-5 6.812549+49128 3 18 4 1.342055-5 6.486598+4 1.480336-5 6.176245+4 1.632865-5 5.880744+49128 3 18 5 1.801111-5 5.599385+4 1.986691-5 5.331491+4 2.191394-5 5.076418+49128 3 18 6 2.417189-5 4.833552+4 2.666248-5 4.602310+4 2.940971-5 4.382134+49128 3 18 7 3.243999-5 4.172496+4 3.578251-5 3.972892+4 3.946943-5 3.782840+49128 3 18 8 4.353624-5 3.601885+4 4.802208-5 3.429591+4 5.297013-5 3.265543+49128 3 18 9 5.842801-5 3.109347+4 6.444825-5 2.960627+4 7.108881-5 2.819026+49128 3 18 10 7.841358-5 2.684202+4 8.649308-5 2.555831+4 9.540506-5 2.433604+49128 3 18 11 1.052353-4 2.317228+4 1.160784-4 2.206422+4 1.280388-4 2.100919+49128 3 18 12 1.412315-4 2.000465+4 1.557836-4 1.904819+4 1.718351-4 1.813751+49128 3 18 13 1.895404-4 1.727040+4 2.090701-4 1.644478+4 2.306120-4 1.565867+49128 3 18 14 2.543736-4 1.491017+4 2.805835-4 1.419748+4 3.094939-4 1.351889+49128 3 18 15 3.413832-4 1.287275+4 3.765583-4 1.225751+4 4.153577-4 1.167170+49128 3 18 16 4.581549-4 1.111390+4 5.053618-4 1.058277+4 5.574328-4 1.007703+49128 3 18 17 6.148689-4 9.595476+3 6.782232-4 9.136940+3 7.481052-4 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