JENDL-5 (Neutron sublibrary (activation cs)) U -230 0 0 0 0 9.223000+4 2.280580+2 0 0 6 19213 1451 1 0.000000+0 1.000000+0 0 0 0 69213 1451 2 1.000000+0 2.000000+7 0 0 10 59213 1451 3 2.936000+2 0.000000+0 4 0 314 129213 1451 4 92-U -230 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9213 1451 5 DIST-DEC21 20100303 9213 1451 6 ----JENDL-5 MATERIAL 9213 9213 1451 7 -----INCIDENT NEUTRON DATA 9213 1451 8 ------ENDF-6 FORMAT 9213 1451 9 9213 1451 10 History 9213 1451 11 07-10 Theoretical calculation was performed with CCONE code. 9213 1451 12 07-11 Data were compiled as JENDL/AC-2008/1/. 9213 1451 13 10-02 Data of prompt gamma rays due to fission were given. 9213 1451 14 10-03 Covariance data were given. 9213 1451 15 21-11 revised by O.Iwamoto 9213 1451 16 (MF3/MT19-21,38) deleted 9213 1451 17 (MF8/MT4,16-18,102) added 9213 1451 18 9213 1451 19 9213 1451 20 MF=1 General information 9213 1451 21 MT=452 Number of Neutrons per fission 9213 1451 22 Sum of MT's=455 and 456. 9213 1451 23 9213 1451 24 MT=455 Delayed neutron data 9213 1451 25 Estimated from systematics by Tuttle/2/, Benedetti et al./3/ 9213 1451 26 and Waldo et al./4/ 9213 1451 27 9213 1451 28 MT=456 Number of prompt neutrons per fission 9213 1451 29 Estimated from Howerton's systematics/5/. 9213 1451 30 9213 1451 31 9213 1451 32 MF= 2 Resonance parameters 9213 1451 33 MT=151 9213 1451 34 No resonance parameters are given. 9213 1451 35 9213 1451 36 9213 1451 37 Thermal cross sections and resonance integrals (at 300K) 9213 1451 38 ------------------------------------------------------- 9213 1451 39 0.0253 eV reson. integ.(*) 9213 1451 40 (barns) (barns) 9213 1451 41 ------------------------------------------------------- 9213 1451 42 total 237.1 9213 1451 43 elastic 11.83 9213 1451 44 fission 25.01 504 9213 1451 45 capture 200.1 138 9213 1451 46 ------------------------------------------------------- 9213 1451 47 (*) In the energy range from 0.5 eV to 10 MeV. 9213 1451 48 9213 1451 49 9213 1451 50 MF= 3 Neutron cross sections 9213 1451 51 Below 2.5 eV: 9213 1451 52 * Elastic scattering cross section is 11.8 b calculated from 9213 1451 53 scattering radius of 9.707 fm/6/. 9213 1451 54 * Fission cross section is in the 1/v shape. 9213 1451 55 Experimental data of 25 b at 0.0253 eV measured by Bentley 9213 1451 56 et al. /7/ was adopted. 9213 1451 57 * Capture cross section is in the 1/v shape. 9213 1451 58 Cross section of 200 b at 0.0253 eV was estimated from 9213 1451 59 systematics. 9213 1451 60 9213 1451 61 Above 2.5 eV: 9213 1451 62 Cross sections calculated with CCONE code/6/ were adopted. 9213 1451 63 9213 1451 64 MT= 1 Total cross section 9213 1451 65 The cross section was calculated with CC OMP of Soukhovitskii 9213 1451 66 et al./8/. 9213 1451 67 9213 1451 68 MT=18 Fission cross section 9213 1451 69 The simulated (n,f) cross sections of Britt and Wilhelmy/9/ 9213 1451 70 were used to determine the parameters in the CCONE 9213 1451 71 calculation. 9213 1451 72 9213 1451 73 9213 1451 74 MF= 4 Angular distributions of secondary neutrons 9213 1451 75 MT=2 Elastic scattering 9213 1451 76 Calculated with CCONE code. 9213 1451 77 9213 1451 78 MT=18 Fission 9213 1451 79 Isotropic distributions in the laboratory system were assumed.9213 1451 80 9213 1451 81 9213 1451 82 MF= 5 Energy distributions of secondary neutrons 9213 1451 83 MT=18 Prompt neutrons 9213 1451 84 Calculated with CCONE code/6/. 9213 1451 85 9213 1451 86 9213 1451 87 MF= 6 Energy-angle distributions 9213 1451 88 Calculated with CCONE code. 9213 1451 89 Distributions from fission (MT=18) are not included. 9213 1451 90 9213 1451 91 9213 1451 92 MF=12 Photon production multiplicities 9213 1451 93 MT=18 Fission 9213 1451 94 Calculated from the total energy released by the prompt 9213 1451 95 gamma-rays due to fission which was estimated from its 9213 1451 96 systematics, and the average energy of gamma-rays. 9213 1451 97 9213 1451 98 9213 1451 99 MF=14 Photon angular distributions 9213 1451 100 MT=18 Fission 9213 1451 101 Isotoropic distributions were assumed. 9213 1451 102 9213 1451 103 9213 1451 104 MF=15 Continuous photon energy spectra 9213 1451 105 MT=18 Fission 9213 1451 106 Experimental data measured by Verbinski et al./10/ for 9213 1451 107 U-235 thermal fission were adopted. 9213 1451 108 9213 1451 109 9213 1451 110 MF=31 Covariances of average number of neutrons per fission 9213 1451 111 MT=452 Number of neutrons per fission 9213 1451 112 Sum of covariances for MT=455 and MT=456. 9213 1451 113 9213 1451 114 MT=455 9213 1451 115 Error of 15% was assumed. 9213 1451 116 9213 1451 117 MT=456 9213 1451 118 Covariance was obtained by fitting a linear function to the 9213 1451 119 at 0.0 and 5.0 MeV with an uncertainty of 5%. 9213 1451 120 9213 1451 121 9213 1451 122 MF=33 Covariances of neutron cross sections 9213 1451 123 Covariances were given to all the cross sections by using 9213 1451 124 KALMAN code/11/ and the covariances of model parameters 9213 1451 125 used in the cross-section calculations. 9213 1451 126 9213 1451 127 For the following cross sections, standard deviations in the 9213 1451 128 energy region below 2.5 eV were assumed as follows: 9213 1451 129 9213 1451 130 Total 77 % 9213 1451 131 Elastic scattering 90 % 9213 1451 132 Fission 90 % 9213 1451 133 Capture 90 % 9213 1451 134 9213 1451 135 9213 1451 136 MF=34 Covariances for Angular Distributions 9213 1451 137 MT=2 Elastic scattering 9213 1451 138 Covariances were given only to P1 components. 9213 1451 139 9213 1451 140 9213 1451 141 MF=35 Covariances for Energy Distributions 9213 1451 142 MT=18 Fission spectra 9213 1451 143 Estimated with CCONE and KALMAN codes. 9213 1451 144 9213 1451 145 9213 1451 146 ***************************************************************** 9213 1451 147 Calculation with CCONE code 9213 1451 148 ***************************************************************** 9213 1451 149 9213 1451 150 Models and parameters used in the CCONE/6/ calculation 9213 1451 151 1) Coupled channel optical model 9213 1451 152 Levels in the rotational band were included. Optical model 9213 1451 153 potential and coupled levels are shown in Table 1. 9213 1451 154 9213 1451 155 2) Two-component exciton model/12/ 9213 1451 156 * Global parametrization of Koning-Duijvestijn/13/ 9213 1451 157 was used. 9213 1451 158 * Gamma emission channel/14/ was added to simulate direct 9213 1451 159 and semi-direct capture reaction. 9213 1451 160 9213 1451 161 3) Hauser-Feshbach statistical model 9213 1451 162 * Moldauer width fluctuation correction/15/ was included. 9213 1451 163 * Neutron, gamma and fission decay channel were included. 9213 1451 164 * Transmission coefficients of neutrons were taken from 9213 1451 165 coupled channel calculation in Table 1. 9213 1451 166 * The level scheme of the target is shown in Table 2. 9213 1451 167 * Level density formula of constant temperature and Fermi-gas 9213 1451 168 model were used with shell energy correction and collective 9213 1451 169 enhancement factor. Parameters are shown in Table 3. 9213 1451 170 * Fission channel: 9213 1451 171 Double humped fission barriers were assumed. 9213 1451 172 Fission barrier penetrabilities were calculated with 9213 1451 173 Hill-Wheler formula/16/. Fission barrier parameters were 9213 1451 174 shown in Table 4. Transition state model was used and 9213 1451 175 continuum levels are assumed above the saddles. The level 9213 1451 176 density parameters for inner and outer saddles are shown in 9213 1451 177 Tables 5 and 6, respectively. 9213 1451 178 * Gamma-ray strength function of Kopecky et al/17/,/18/ 9213 1451 179 was used. The prameters are shown in Table 7. 9213 1451 180 9213 1451 181 9213 1451 182 ------------------------------------------------------------------9213 1451 183 Tables 9213 1451 184 ------------------------------------------------------------------9213 1451 185 9213 1451 186 Table 1. Coupled channel calculation 9213 1451 187 -------------------------------------------------- 9213 1451 188 * rigid rotor model was applied 9213 1451 189 * coupled levels = 0,1,2,3,7 (see Table 2) 9213 1451 190 * optical potential parameters /8/ 9213 1451 191 Volume: 9213 1451 192 V_0 = 49.97 MeV 9213 1451 193 lambda_HF = 0.01004 1/MeV 9213 1451 194 C_viso = 15.9 MeV 9213 1451 195 A_v = 12.04 MeV 9213 1451 196 B_v = 81.36 MeV 9213 1451 197 E_a = 385 MeV 9213 1451 198 r_v = 1.2568 fm 9213 1451 199 a_v = 0.633 fm 9213 1451 200 Surface: 9213 1451 201 W_0 = 17.2 MeV 9213 1451 202 B_s = 11.19 MeV 9213 1451 203 C_s = 0.01361 1/MeV 9213 1451 204 C_wiso = 23.5 MeV 9213 1451 205 r_s = 1.1803 fm 9213 1451 206 a_s = 0.601 fm 9213 1451 207 Spin-orbit: 9213 1451 208 V_so = 5.75 MeV 9213 1451 209 lambda_so = 0.005 1/MeV 9213 1451 210 W_so = -3.1 MeV 9213 1451 211 B_so = 160 MeV 9213 1451 212 r_so = 1.1214 fm 9213 1451 213 a_so = 0.59 fm 9213 1451 214 Coulomb: 9213 1451 215 C_coul = 1.3 9213 1451 216 r_c = 1.2452 fm 9213 1451 217 a_c = 0.545 fm 9213 1451 218 Deformation: 9213 1451 219 beta_2 = 0.213 9213 1451 220 beta_4 = 0.066 9213 1451 221 beta_6 = 0.0015 9213 1451 222 9213 1451 223 * Calculated strength function 9213 1451 224 S0= 1.13e-4 S1= 2.55e-4 R'= 9.71 fm (En=1 keV) 9213 1451 225 -------------------------------------------------- 9213 1451 226 9213 1451 227 Table 2. Level Scheme of U-230 9213 1451 228 ------------------- 9213 1451 229 No. Ex(MeV) J PI 9213 1451 230 ------------------- 9213 1451 231 0 0.00000 0 + * 9213 1451 232 1 0.05172 2 + * 9213 1451 233 2 0.16950 4 + * 9213 1451 234 3 0.34710 6 + * 9213 1451 235 4 0.36656 1 - 9213 1451 236 5 0.43530 3 - 9213 1451 237 6 0.55830 5 - 9213 1451 238 7 0.57820 8 + * 9213 1451 239 8 0.73410 7 - 9213 1451 240 ------------------- 9213 1451 241 *) Coupled levels in CC calculation 9213 1451 242 9213 1451 243 Table 3. Level density parameters 9213 1451 244 -------------------------------------------------------- 9213 1451 245 Nuclide a* Pair Eshell T E0 Ematch 9213 1451 246 1/MeV MeV MeV MeV MeV MeV 9213 1451 247 -------------------------------------------------------- 9213 1451 248 U-231 18.2614 0.7895 2.6793 0.3780 -0.7805 2.9483 9213 1451 249 U-230 18.1935 1.5825 2.6739 0.3937 -0.1508 3.9419 9213 1451 250 U-229 18.1256 0.7930 2.8715 0.3807 -0.8108 2.9930 9213 1451 251 U-228 18.0576 1.5894 2.8045 0.3969 -0.1770 3.9894 9213 1451 252 -------------------------------------------------------- 9213 1451 253 9213 1451 254 Table 4. Fission barrier parameters 9213 1451 255 ---------------------------------------- 9213 1451 256 Nuclide V_A hw_A V_B hw_B 9213 1451 257 MeV MeV MeV MeV 9213 1451 258 ---------------------------------------- 9213 1451 259 U-231 6.000 0.800 5.600 0.520 9213 1451 260 U-230 5.800 1.040 5.100 0.600 9213 1451 261 U-229 6.000 0.800 5.600 0.520 9213 1451 262 U-228 5.800 1.040 5.100 0.600 9213 1451 263 ---------------------------------------- 9213 1451 264 9213 1451 265 Table 5. Level density above inner saddle 9213 1451 266 -------------------------------------------------------- 9213 1451 267 Nuclide a* Pair Eshell T E0 Ematch 9213 1451 268 1/MeV MeV MeV MeV MeV MeV 9213 1451 269 -------------------------------------------------------- 9213 1451 270 U-231 21.4840 0.9211 2.6000 0.3544 -1.9793 3.4211 9213 1451 271 U-230 19.9772 1.8463 2.6000 0.3332 -0.5651 3.8463 9213 1451 272 U-229 19.9026 0.9251 2.6000 0.3339 -1.4862 2.9251 9213 1451 273 U-228 19.8280 1.8543 2.6000 0.3346 -0.5570 3.8543 9213 1451 274 -------------------------------------------------------- 9213 1451 275 9213 1451 276 Table 6. Level density above outer saddle 9213 1451 277 -------------------------------------------------------- 9213 1451 278 Nuclide a* Pair Eshell T E0 Ematch 9213 1451 279 1/MeV MeV MeV MeV MeV MeV 9213 1451 280 -------------------------------------------------------- 9213 1451 281 U-231 21.4840 0.9211 -0.0600 0.3957 -1.1784 3.4211 9213 1451 282 U-230 19.9772 1.8463 -0.1000 0.3771 0.1493 3.8463 9213 1451 283 U-229 19.9026 0.9251 -0.1400 0.3784 -0.7712 2.9251 9213 1451 284 U-228 19.8280 1.8543 -0.1800 0.3798 0.1586 3.8543 9213 1451 285 -------------------------------------------------------- 9213 1451 286 9213 1451 287 Table 7. Gamma-ray strength function for U-231 9213 1451 288 -------------------------------------------------------- 9213 1451 289 K0 = 1.502 E0 = 4.500 (MeV) 9213 1451 290 * E1: ER = 10.90 (MeV) EG = 2.50 (MeV) SIG = 300.00 (mb) 9213 1451 291 ER = 13.80 (MeV) EG = 4.70 (MeV) SIG = 450.00 (mb) 9213 1451 292 * M1: ER = 6.68 (MeV) EG = 4.00 (MeV) SIG = 2.71 (mb) 9213 1451 293 * E2: ER = 10.27 (MeV) EG = 3.34 (MeV) SIG = 6.54 (mb) 9213 1451 294 -------------------------------------------------------- 9213 1451 295 9213 1451 296 9213 1451 297 References 9213 1451 298 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9213 1451 299 2) R.J.Tuttle: INDC(NDS)-107/G+Special, p.29 (1979). 9213 1451 300 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 9213 1451 301 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 9213 1451 302 5) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9213 1451 303 6) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9213 1451 304 7) W.Bentley et al.: CC-3699, p.6 (1946). 9213 1451 305 8) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9213 1451 306 9) H.C.Britt, J.B.Wilhelmy: Nucl. Sci. Eng., 72, 222 (1979) 9213 1451 307 10) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9213 1451 308 11) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9213 1451 309 Japanese. 9213 1451 310 12) C.Kalbach: Phys. Rev. C33, 818 (1986). 9213 1451 311 13) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9213 1451 312 14) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9213 1451 313 15) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9213 1451 314 16) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9213 1451 315 17) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9213 1451 316 18) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9213 1451 317 9213 1451 318 1 451 330 19213 1451 319 2 151 4 19213 1451 320 3 4 27 19213 1451 321 3 16 12 19213 1451 322 3 17 8 19213 1451 323 3 18 140 19213 1451 324 3 102 149 19213 1451 325 8 4 2 19213 1451 326 8 16 2 19213 1451 327 8 17 2 19213 1451 328 8 18 2 19213 1451 329 8 102 2 19213 1451 330 9213 1 099999 9213 0 0 0 9.223000+4 2.280580+2 0 0 1 09213 2151 1 9.223000+4 1.000000+0 0 0 1 09213 2151 2 1.000000-5 2.500000+0 0 0 0 09213 2151 3 0.000000+0 9.707000-1 0 0 0 09213 2151 4 9213 2 099999 9213 0 0 0 9.223000+4 2.280580+2 0 0 0 09213 3 4 1 0.000000+0-5.172000+4 0 0 1 729213 3 4 2 72 2 9213 3 4 3 5.194680+4 0.000000+0 7.000000+4 4.040650-2 1.000000+5 1.334970-19213 3 4 4 1.109670+5 1.630706-1 1.200000+5 1.874303-1 1.400000+5 2.354537-19213 3 4 5 1.700000+5 2.998176-1 1.702430+5 3.003096-1 2.000000+5 3.601454-19213 3 4 6 2.500000+5 4.204332-1 3.000000+5 4.726538-1 3.486220+5 4.900710-19213 3 4 7 3.681670+5 4.958843-1 4.000000+5 5.677414-1 4.372090+5 6.130128-19213 3 4 8 5.000000+5 6.828391-1 5.607480+5 7.082207-1 5.807350+5 7.136436-19213 3 4 9 6.000000+5 7.183537-1 7.000000+5 7.399731-1 7.373190+5 7.379316-19213 3 4 10 8.000000+5 7.306915-1 9.000000+5 7.274068-1 1.000000+6 7.376848-19213 3 4 11 1.100000+6 7.506068-1 1.200000+6 7.662304-1 1.300000+6 7.845734-19213 3 4 12 1.400000+6 8.052913-1 1.500000+6 8.254334-1 1.600000+6 8.458938-19213 3 4 13 1.700000+6 8.641000-1 1.800000+6 8.823925-1 1.900000+6 8.975217-19213 3 4 14 2.000000+6 9.123675-1 2.300000+6 9.424110-1 2.500000+6 9.549310-19213 3 4 15 2.700000+6 9.858561-1 3.000000+6 1.011441+0 3.500000+6 1.042802+09213 3 4 16 4.000000+6 1.085649+0 4.500000+6 1.145314+0 5.000000+6 1.194833+09213 3 4 17 5.500000+6 1.153628+0 6.000000+6 1.037335+0 6.500000+6 9.247883-19213 3 4 18 7.000000+6 8.402302-1 7.500000+6 7.775978-1 8.000000+6 7.287662-19213 3 4 19 8.500000+6 6.882599-1 9.000000+6 6.531929-1 9.500000+6 6.219257-19213 3 4 20 1.000000+7 5.934456-1 1.050000+7 5.668945-1 1.100000+7 5.419483-19213 3 4 21 1.150000+7 5.186025-1 1.200000+7 4.960061-1 1.250000+7 4.743859-19213 3 4 22 1.300000+7 4.537123-1 1.350000+7 4.343109-1 1.400000+7 4.155801-19213 3 4 23 1.450000+7 3.978466-1 1.500000+7 3.811403-1 1.550000+7 3.657071-19213 3 4 24 1.600000+7 3.508807-1 1.650000+7 3.377750-1 1.700000+7 3.250466-19213 3 4 25 1.750000+7 3.136745-1 1.800000+7 3.028714-1 1.850000+7 2.932571-19213 3 4 26 1.900000+7 2.841519-1 1.950000+7 2.760707-1 2.000000+7 2.684168-19213 3 4 27 9213 3 099999 9.223000+4 2.280580+2 0 0 0 09213 3 16 1 -7.667190+6-7.667190+6 0 0 1 269213 3 16 2 26 2 9213 3 16 3 7.700810+6 0.000000+0 8.000000+6 1.773480-4 8.500000+6 4.171480-39213 3 16 4 9.000000+6 1.374980-2 9.500000+6 2.509750-2 1.000000+7 3.581740-29213 3 16 5 1.050000+7 4.617650-2 1.100000+7 5.591290-2 1.150000+7 6.815300-29213 3 16 6 1.200000+7 8.384660-2 1.250000+7 1.032180-1 1.300000+7 1.252510-19213 3 16 7 1.350000+7 1.499180-1 1.400000+7 1.735700-1 1.450000+7 1.891030-19213 3 16 8 1.500000+7 1.938220-1 1.550000+7 1.891140-1 1.600000+7 1.774040-19213 3 16 9 1.650000+7 1.629270-1 1.700000+7 1.472170-1 1.750000+7 1.320710-19213 3 16 10 1.800000+7 1.178650-1 1.850000+7 1.063110-1 1.900000+7 9.600870-29213 3 16 11 1.950000+7 8.742760-2 2.000000+7 8.059120-2 9213 3 16 12 9213 3 099999 9.223000+4 2.280580+2 0 0 0 09213 3 17 1 -1.375260+7-1.375260+7 0 0 1 139213 3 17 2 13 2 9213 3 17 3 1.381290+7 0.000000+0 1.450000+7 4.637540-5 1.500000+7 5.786340-49213 3 17 4 1.550000+7 2.476530-3 1.600000+7 6.418210-3 1.650000+7 1.242910-29213 3 17 5 1.700000+7 1.749900-2 1.750000+7 2.301570-2 1.800000+7 3.110020-29213 3 17 6 1.850000+7 3.687440-2 1.900000+7 4.292460-2 1.950000+7 4.957200-29213 3 17 7 2.000000+7 5.526710-2 9213 3 17 8 9213 3 099999 9.223000+4 2.280580+2 0 0 0 09213 3 18 1 1.868000+8 1.868000+8 0 0 1 4119213 3 18 2 411 2 9213 3 18 3 1.000000-5 1.259200+3 1.103037-5 1.198944+3 1.216691-5 1.141572+39213 3 18 4 1.342055-5 1.086945+3 1.480336-5 1.034931+3 1.632865-5 9.854067+29213 3 18 5 1.801111-5 9.382519+2 1.986691-5 8.933534+2 2.191394-5 8.506032+29213 3 18 6 2.417189-5 8.098985+2 2.666248-5 7.711415+2 2.940971-5 7.342390+29213 3 18 7 3.243999-5 6.991021+2 3.578251-5 6.656465+2 3.946943-5 6.337916+29213 3 18 8 4.353624-5 6.034609+2 4.802208-5 5.745815+2 5.297013-5 5.470838+29213 3 18 9 5.842801-5 5.209018+2 6.444825-5 4.959726+2 7.108881-5 4.722361+29213 3 18 10 7.841358-5 4.496353+2 8.649308-5 4.281159+2 9.540506-5 4.076261+29213 3 18 11 1.052353-4 3.881167+2 1.160784-4 3.695407+2 1.280388-4 3.518536+29213 3 18 12 1.412315-4 3.350127+2 1.557836-4 3.189777+2 1.718351-4 3.037099+29213 3 18 13 1.895404-4 2.891727+2 2.090701-4 2.753311+2 2.306120-4 2.621518+29213 3 18 14 2.543736-4 2.496033+2 2.805835-4 2.376552+2 3.094939-4 2.262789+29213 3 18 15 3.413832-4 2.154470+2 3.765583-4 2.051335+2 4.153577-4 1.953137+29213 3 18 16 4.581549-4 1.859638+2 5.053618-4 1.770614+2 5.574328-4 1.685852+29213 3 18 17 6.148689-4 1.605146+2 6.782232-4 1.528304+2 7.481052-4 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