JENDL-5 (Neutron sublibrary (activation cs)) Ru- 96 0 0 0 0 4.409600+4 9.508371+1 0 0 6 14425 1451 1 0.000000+0 0.000000+0 0 0 0 64425 1451 2 1.000000+0 2.000000+7 0 0 10 54425 1451 3 2.936000+2 0.000000+0 4 0 432 244425 1451 4 44-Ru- 96 JAEA EVAL-APR13 K.Shibata 4425 1451 5 JNST 50, 1177 (2013) DIST-DEC21 20180517 4425 1451 6 ----JENDL-5 MATERIAL 4425 4425 1451 7 -----INCIDENT NEUTRON DATA 4425 1451 8 ------ENDF-6 FORMAT 4425 1451 9 4425 1451 10 History 4425 1451 11 12-07 The fast neutron cross sections were re-evaluated by 4425 1451 12 K.Shibata (JAEA) /1/ using the POD code /2/. 4425 1451 13 13-02 The thermal capture cross section was revised by considering4425 1451 14 the latest measurements. 4425 1451 15 13-04 The fast neutron cross sections were re-calculated by 4425 1451 16 using slightly modified model parameters. 4425 1451 17 13-10 The (n,np) cross section for the ground state was modified 4425 1451 18 by considering experimental data. 4425 1451 19 18-05 Activation cross sections added by K.Shibata. 4425 1451 20 21-11 revised by O.Iwamoto 4425 1451 21 (MF8/MT4) added 4425 1451 22 21-11 above 20 MeV, JENDL/ImPACT-2018 merged by O.Iwamoto 4425 1451 23 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 4425 1451 24 4425 1451 25 4425 1451 26 MF= 1 General information 4425 1451 27 MT=451 Descriptive data and directory 4425 1451 28 4425 1451 29 MF= 2 Resonance parameters 4425 1451 30 MT=151 Resolved and unresolved resonance parameters 4425 1451 31 No resolved resonance parameters are given. 4425 1451 32 4425 1451 33 Unresolved resonance region: 170 eV - 300 keV 4425 1451 34 The parameters were obtained by fitting to the calculated 4425 1451 35 total and capture cross sections. The unresolved resonance 4425 1451 36 parameters obtained should be used only for self-shielding 4425 1451 37 calculation. URP's were re-calculated by fitting to the 4425 1451 38 total and capture cross sections calculated by POD /2/. 4425 1451 39 4425 1451 40 Thermal cross sections and resonance integrals at 300 K 4425 1451 41 ---------------------------------------------------------- 4425 1451 42 0.0253 eV res. integ. (*) 4425 1451 43 (barns) (barns) 4425 1451 44 ---------------------------------------------------------- 4425 1451 45 Total 5.2357E+00 4425 1451 46 Elastic 5.0301E+00 4425 1451 47 n,gamma 2.0710E-01 6.2716E+00 4425 1451 48 ---------------------------------------------------------- 4425 1451 49 (*) Integrated from 0.5 eV to 10 MeV. 4425 1451 50 4425 1451 51 MF= 3 Neutron cross sections 4425 1451 52 MT= 1 Total cross section 4425 1451 53 Calculated with POD code /2/. Below 170 eV, the cross 4425 1451 54 sections were obtained by summing up the partial cross 4425 1451 55 cross sections. 4425 1451 56 4425 1451 57 MT= 2 Elastic scattering cross section 4425 1451 58 Below 170 eV, the constant cross section is the same as that 4425 1451 59 for JENDL-4.0, i.e., 5.0 b. Above 170 eV, the cross section 4425 1451 60 was obtained by subtracting the non-elastic cross section 4425 1451 61 from the total cross section. 4425 1451 62 4425 1451 63 MT= 3 Non-elastic cross section 4425 1451 64 Calculated with POD code /2/. 4425 1451 65 4425 1451 66 MT= 4,51-91 (n,n') cross section 4425 1451 67 Calculated with POD code /2/. 4425 1451 68 4425 1451 69 MT= 16 (n,2n) cross section 4425 1451 70 Calculated with POD code /2/. 4425 1451 71 4425 1451 72 MT= 22 (n,na) cross section 4425 1451 73 Calculated with POD code /2/. 4425 1451 74 4425 1451 75 MT= 28 (n,np) cross section 4425 1451 76 Calculated with POD code /2/. 4425 1451 77 4425 1451 78 MT= 32 (n,nd) cross section 4425 1451 79 Calculated with POD code /2/. 4425 1451 80 4425 1451 81 MT=102 Capture cross section 4425 1451 82 Calculated with POD code /2/. Below 170 eV, the 1/v 4425 1451 83 cross section was assumed with 0.207 b at 0.0253 eV./3/ 4425 1451 84 4425 1451 85 MT=103 (n,p) cross section 4425 1451 86 Calculated with POD code /2/. 4425 1451 87 4425 1451 88 MT=104 (n,d) cross section 4425 1451 89 Calculated with POD code /2/. 4425 1451 90 4425 1451 91 MT=105 (n,t) cross section 4425 1451 92 Calculated with POD code /2/. 4425 1451 93 4425 1451 94 MT=106 (n,He3) cross section 4425 1451 95 Calculated with POD code /2/. 4425 1451 96 4425 1451 97 MT=107 (n,a) cross section 4425 1451 98 Calculated with POD code /2/. 4425 1451 99 4425 1451 100 MT=203 (n,xp) cross section 4425 1451 101 Calculated with POD code /2/. 4425 1451 102 4425 1451 103 MT=204 (n,xd) cross section 4425 1451 104 Calculated with POD code /2/. 4425 1451 105 4425 1451 106 MT=205 (n,xt) cross section 4425 1451 107 Calculated with POD code /2/. 4425 1451 108 4425 1451 109 MT=206 (n,xHe3) cross section 4425 1451 110 Calculated with POD code /2/. 4425 1451 111 4425 1451 112 MT=207 (n,xa) cross section 4425 1451 113 Calculated with POD code /2/. 4425 1451 114 4425 1451 115 MF= 4 Angular distributions of emitted neutrons 4425 1451 116 MT= 2 Elastic scattering 4425 1451 117 Calculated with POD code /2/. 4425 1451 118 4425 1451 119 MF= 6 Energy-angle distributions of emitted particles 4425 1451 120 MT= 16 (n,2n) reaction 4425 1451 121 Neutron spectra calculated with POD/2/. 4425 1451 122 4425 1451 123 MT= 22 (n,na) reaction 4425 1451 124 Neutron spectra calculated with POD/2/. 4425 1451 125 4425 1451 126 MT= 28 (n,np) reaction 4425 1451 127 Neutron spectra calculated with POD/2/. 4425 1451 128 4425 1451 129 MT= 32 (n,nd) reaction 4425 1451 130 Neutron spectra calculated with POD/2/. 4425 1451 131 4425 1451 132 MT= 51 (n,n') reaction 4425 1451 133 Neutron angular distributions calculated with POD/2/. 4425 1451 134 4425 1451 135 MT= 52 (n,n') reaction 4425 1451 136 Neutron angular distributions calculated with POD/2/. 4425 1451 137 4425 1451 138 MT= 53 (n,n') reaction 4425 1451 139 Neutron angular distributions calculated with POD/2/. 4425 1451 140 4425 1451 141 MT= 54 (n,n') reaction 4425 1451 142 Neutron angular distributions calculated with POD/2/. 4425 1451 143 4425 1451 144 MT= 55 (n,n') reaction 4425 1451 145 Neutron angular distributions calculated with POD/2/. 4425 1451 146 4425 1451 147 MT= 56 (n,n') reaction 4425 1451 148 Neutron angular distributions calculated with POD/2/. 4425 1451 149 4425 1451 150 MT= 57 (n,n') reaction 4425 1451 151 Neutron angular distributions calculated with POD/2/. 4425 1451 152 4425 1451 153 MT= 58 (n,n') reaction 4425 1451 154 Neutron angular distributions calculated with POD/2/. 4425 1451 155 4425 1451 156 MT= 59 (n,n') reaction 4425 1451 157 Neutron angular distributions calculated with POD/2/. 4425 1451 158 4425 1451 159 MT= 60 (n,n') reaction 4425 1451 160 Neutron angular distributions calculated with POD/2/. 4425 1451 161 4425 1451 162 MT= 61 (n,n') reaction 4425 1451 163 Neutron angular distributions calculated with POD/2/. 4425 1451 164 4425 1451 165 MT= 62 (n,n') reaction 4425 1451 166 Neutron angular distributions calculated with POD/2/. 4425 1451 167 4425 1451 168 MT= 63 (n,n') reaction 4425 1451 169 Neutron angular distributions calculated with POD/2/. 4425 1451 170 4425 1451 171 MT= 64 (n,n') reaction 4425 1451 172 Neutron angular distributions calculated with POD/2/. 4425 1451 173 4425 1451 174 MT= 65 (n,n') reaction 4425 1451 175 Neutron angular distributions calculated with POD/2/. 4425 1451 176 4425 1451 177 MT= 66 (n,n') reaction 4425 1451 178 Neutron angular distributions calculated with POD/2/. 4425 1451 179 4425 1451 180 MT= 67 (n,n') reaction 4425 1451 181 Neutron angular distributions calculated with POD/2/. 4425 1451 182 4425 1451 183 MT= 68 (n,n') reaction 4425 1451 184 Neutron angular distributions calculated with POD/2/. 4425 1451 185 4425 1451 186 MT= 69 (n,n') reaction 4425 1451 187 Neutron angular distributions calculated with POD/2/. 4425 1451 188 4425 1451 189 MT= 70 (n,n') reaction 4425 1451 190 Neutron angular distributions calculated with POD/2/. 4425 1451 191 4425 1451 192 MT= 71 (n,n') reaction 4425 1451 193 Neutron angular distributions calculated with POD/2/. 4425 1451 194 4425 1451 195 MT= 72 (n,n') reaction 4425 1451 196 Neutron angular distributions calculated with POD/2/. 4425 1451 197 4425 1451 198 MT= 73 (n,n') reaction 4425 1451 199 Neutron angular distributions calculated with POD/2/. 4425 1451 200 4425 1451 201 MT= 74 (n,n') reaction 4425 1451 202 Neutron angular distributions calculated with POD/2/. 4425 1451 203 4425 1451 204 MT= 75 (n,n') reaction 4425 1451 205 Neutron angular distributions calculated with POD/2/. 4425 1451 206 4425 1451 207 MT= 76 (n,n') reaction 4425 1451 208 Neutron angular distributions calculated with POD/2/. 4425 1451 209 4425 1451 210 MT= 77 (n,n') reaction 4425 1451 211 Neutron angular distributions calculated with POD/2/. 4425 1451 212 4425 1451 213 MT= 78 (n,n') reaction 4425 1451 214 Neutron angular distributions calculated with POD/2/. 4425 1451 215 4425 1451 216 MT= 79 (n,n') reaction 4425 1451 217 Neutron angular distributions calculated with POD/2/. 4425 1451 218 4425 1451 219 MT= 80 (n,n') reaction 4425 1451 220 Neutron angular distributions calculated with POD/2/. 4425 1451 221 4425 1451 222 MT= 81 (n,n') reaction 4425 1451 223 Neutron angular distributions calculated with POD/2/. 4425 1451 224 4425 1451 225 MT= 82 (n,n') reaction 4425 1451 226 Neutron angular distributions calculated with POD/2/. 4425 1451 227 4425 1451 228 MT= 83 (n,n') reaction 4425 1451 229 Neutron angular distributions calculated with POD/2/. 4425 1451 230 4425 1451 231 MT= 84 (n,n') reaction 4425 1451 232 Neutron angular distributions calculated with POD/2/. 4425 1451 233 4425 1451 234 MT= 85 (n,n') reaction 4425 1451 235 Neutron angular distributions calculated with POD/2/. 4425 1451 236 4425 1451 237 MT= 86 (n,n') reaction 4425 1451 238 Neutron angular distributions calculated with POD/2/. 4425 1451 239 4425 1451 240 MT= 87 (n,n') reaction 4425 1451 241 Neutron angular distributions calculated with POD/2/. 4425 1451 242 4425 1451 243 MT= 91 (n,n') reaction 4425 1451 244 Neutron spectra calculated with POD/2/. 4425 1451 245 4425 1451 246 MT= 203 (n,xp) reaction 4425 1451 247 Proton spectra calculated with POD/2/. 4425 1451 248 4425 1451 249 MT= 204 (n,xd) reaction 4425 1451 250 Deuteron spectra calculated with POD/2/. 4425 1451 251 4425 1451 252 MT= 205 (n,xt) reaction 4425 1451 253 Triton spectra calculated with POD/2/. 4425 1451 254 4425 1451 255 MT= 206 (n,xHe3) reaction 4425 1451 256 He3 spectra calculated with POD/2/. 4425 1451 257 4425 1451 258 MT= 207 (n,xa) reaction 4425 1451 259 Alpha spectra calculated with POD/2/. 4425 1451 260 4425 1451 261 MF= 8 Information on decay data 4425 1451 262 MT= 16 (n,2n) reaction 4425 1451 263 4425 1451 264 MT= 22 (n,na) reaction 4425 1451 265 4425 1451 266 MT= 28 (n,np) reaction 4425 1451 267 4425 1451 268 MT= 32 (n,nd) reaction 4425 1451 269 4425 1451 270 MT=102 (n,g) reaction 4425 1451 271 4425 1451 272 MT=103 (n,p) reaction 4425 1451 273 4425 1451 274 MT=104 (n,d) reaction 4425 1451 275 4425 1451 276 MT=105 (n,t) reaction 4425 1451 277 4425 1451 278 MT=106 (n,He3) reaction 4425 1451 279 4425 1451 280 MT=107 (n,a) reaction 4425 1451 281 4425 1451 282 MF=10 Nuclide production cross sections 4425 1451 283 MT= 28 Partial (n,np) reactions 4425 1451 284 Calculated with POD code /2/. 4425 1451 285 For the ground state, the cross section was multiplied by 1.7 4425 1451 286 above 13 MeV. 4425 1451 287 4425 1451 288 MT= 32 Partial (n,nd) reactions 4425 1451 289 Calculated with POD code /2/. 4425 1451 290 4425 1451 291 MT=103 Partial (n,p) reactions 4425 1451 292 Calculated with POD code /2/. 4425 1451 293 4425 1451 294 MT=104 Partial (n,d) reactions 4425 1451 295 Calculated with POD code /2/. 4425 1451 296 4425 1451 297 MT=105 Partial (n,t) reactions 4425 1451 298 Calculated with POD code /2/. 4425 1451 299 4425 1451 300 MT=107 Partial (n,a) reactions 4425 1451 301 Calculated with POD code /2/. 4425 1451 302 4425 1451 303 MF=12 Gamma-ray multiplicities 4425 1451 304 MT= 3 Non-elastic gamma emission 4425 1451 305 Calculated with POD code /2/. 4425 1451 306 4425 1451 307 MF=14 Gamma-ray angular distributions 4425 1451 308 MT= 3 Non-elastic gamma emission 4425 1451 309 Assumed to be isotropic. 4425 1451 310 4425 1451 311 MF=15 Gamma-ray spectra 4425 1451 312 MT= 3 Non-elastic gamma emission 4425 1451 313 Calculated with POD code /2/. 4425 1451 314 4425 1451 315 4425 1451 316 4425 1451 317 *************************************************************** 4425 1451 318 * Nuclear Model Calculations with POD Code /2/ * 4425 1451 319 *************************************************************** 4425 1451 320 1. Theoretical models 4425 1451 321 The POD code is based on the spherical optical model, the 4425 1451 322 distorted-wave Born approximaiton (DWBA), one-component exciton 4425 1451 323 preequilibrium model, and the Hauser-Feshbach-Moldauer statis- 4425 1451 324 tical model. With the preequilibrim model, semi-empirical 4425 1451 325 pickup and knockout process can be taken into account for 4425 1451 326 composite-particle emission. The gamma-ray emission from the 4425 1451 327 compound nucleus can be calculated within the framework of the 4425 1451 328 exciton model. The code is capable of reading in particle 4425 1451 329 transmission coefficients calculated by separate spherical or 4425 1451 330 coupled-channel optical model code. 4425 1451 331 4425 1451 332 2. Optical model parameters 4425 1451 333 Neutrons: 4425 1451 334 Coupled-channel optical model parameters /4/ 4425 1451 335 Protons: 4425 1451 336 Koning and Delaroche /5/ 4425 1451 337 Deuterons: 4425 1451 338 Lohr and Haeberli /6/ 4425 1451 339 Tritons: 4425 1451 340 Becchetti and Greenlees /7/ 4425 1451 341 He-3: 4425 1451 342 Becchetti and Greenlees /7/ 4425 1451 343 Alphas: 4425 1451 344 Lemos /8/ potentials modified by Arthur and Young /9/ 4425 1451 345 4425 1451 346 3. Level scheme of Ru- 96 4425 1451 347 ------------------------- 4425 1451 348 No. Ex(MeV) J PI 4425 1451 349 ------------------------- 4425 1451 350 0 0.00000 0 + 4425 1451 351 1* 0.83257 2 + 4425 1451 352 2* 1.51806 4 + 4425 1451 353 3 1.93108 2 + 4425 1451 354 4 2.14880 0 + 4425 1451 355 5 2.14977 6 + 4425 1451 356 6 2.28420 2 + 4425 1451 357 7 2.46207 5 + 4425 1451 358 8 2.52460 3 + 4425 1451 359 9 2.52840 2 + 4425 1451 360 10 2.57610 1 + 4425 1451 361 11* 2.57900 3 - 4425 1451 362 12 2.58840 5 - 4425 1451 363 13 2.65000 3 - 4425 1451 364 14 2.70010 4 + 4425 1451 365 15 2.73980 3 + 4425 1451 366 16 2.76020 5 - 4425 1451 367 17 2.79384 6 - 4425 1451 368 18 2.85140 3 + 4425 1451 369 19 2.89164 6 + 4425 1451 370 20 2.89770 3 + 4425 1451 371 21 2.95040 8 + 4425 1451 372 22 2.98780 3 - 4425 1451 373 23 2.99640 2 - 4425 1451 374 24 3.06050 2 - 4425 1451 375 25 3.07590 3 - 4425 1451 376 26 3.07654 4 - 4425 1451 377 27 3.09020 2 - 4425 1451 378 28 3.16669 4 - 4425 1451 379 29 3.21010 2 - 4425 1451 380 30 3.23210 2 + 4425 1451 381 31 3.26098 2 + 4425 1451 382 32 3.29100 7 - 4425 1451 383 33 3.29160 6 + 4425 1451 384 34 3.30672 6 + 4425 1451 385 35 3.36250 6 + 4425 1451 386 36 3.37753 6 + 4425 1451 387 37 3.38047 6 + 4425 1451 388 ------------------------- 4425 1451 389 Levels above 3.39047 MeV are assumed to be continuous. 4425 1451 390 The symbol (*) stands for the excited level involved in the 4425 1451 391 coupled-channel calculation. 4425 1451 392 4425 1451 393 4. Level density parameters 4425 1451 394 Energy-dependent parameters of Mengoni-Nakajima /10/ were used 4425 1451 395 ---------------------------------------------------------- 4425 1451 396 Nuclei a* Pair Esh T E0 Ematch Elv_max 4425 1451 397 1/MeV MeV MeV MeV MeV MeV MeV 4425 1451 398 ---------------------------------------------------------- 4425 1451 399 Ru- 97 13.206 1.218 -1.096 0.800 -0.497 6.858 2.020 4425 1451 400 Ru- 96 12.406 2.449 -2.111 1.033 -0.854 11.220 3.380 4425 1451 401 Ru- 95 12.989 1.231 -3.160 0.951 -0.738 7.930 2.294 4425 1451 402 Ru- 94 12.188 2.475 -4.075 1.098 0.129 10.385 3.255 4425 1451 403 Tc- 96 12.363 0.000 -0.160 0.891 -2.708 7.312 0.789 4425 1451 404 Tc- 95 11.776 1.231 -0.948 1.009 -2.035 9.820 1.785 4425 1451 405 Tc- 94 12.147 0.000 -2.297 0.771 -0.448 3.806 2.135 4425 1451 406 Mo- 94 12.188 2.475 -0.706 0.937 -0.373 10.175 2.956 4425 1451 407 Mo- 93 12.764 1.244 -1.843 0.892 -0.799 7.716 2.755 4425 1451 408 Mo- 92 11.969 2.502 -2.668 0.948 0.891 8.698 4.019 4425 1451 409 ---------------------------------------------------------- 4425 1451 410 4425 1451 411 5. Gamma-ray strength functions 4425 1451 412 M1, E2: Standard Lorentzian (SLO) 4425 1451 413 E1 : Modified Lorentzian (MLO) /11/ 4425 1451 414 4425 1451 415 6. Preequilibrium process 4425 1451 416 Preequilibrium is on for n, p, d, t, He-3, and alpha. 4425 1451 417 Preequilibrium capture is on. 4425 1451 418 4425 1451 419 References 4425 1451 420 1) K.Shibata, J. Nucl. Sci. Technol., 50, 1177 (2013). 4425 1451 421 2) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 4425 1451 422 3) K.S.Krane, Phys. Rev. C81, 044310 (2010). 4425 1451 423 4) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 4425 1451 424 5) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 4425 1451 425 6) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 4425 1451 426 7) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization 4425 1451 427 Phenomena in Nuclear Reactions," p.682, The University 4425 1451 428 of Wisconsin Press (1971). 4425 1451 429 8) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 4425 1451 430 9) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 4425 1451 431 10) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 4425 1451 432 (1994). 4425 1451 433 11) V.A.Plujko et al., J. Nucl. Sci. Technol. Suppl. 2, 811 4425 1451 434 (2002). 4425 1451 435 4425 1451 436 1 451 460 14425 1451 437 2 151 4 14425 1451 438 3 4 27 14425 1451 439 3 16 7 14425 1451 440 3 22 9 14425 1451 441 3 102 134 14425 1451 442 3 106 8 14425 1451 443 8 4 2 14425 1451 444 8 16 2 14425 1451 445 8 22 2 14425 1451 446 8 28 3 14425 1451 447 8 32 3 14425 1451 448 8 102 2 14425 1451 449 8 103 3 14425 1451 450 8 104 3 14425 1451 451 8 105 3 14425 1451 452 8 106 2 14425 1451 453 8 107 3 14425 1451 454 10 28 15 14425 1451 455 10 32 9 14425 1451 456 10 103 25 14425 1451 457 10 104 17 14425 1451 458 10 105 13 14425 1451 459 10 107 27 14425 1451 460 4425 1 099999 4425 0 0 0 4.409600+4 9.508371+1 0 0 1 04425 2151 1 4.409600+4 1.000000+0 0 0 1 04425 2151 2 1.700000+2 3.000000+5 0 0 0 04425 2151 3 0.000000+0 6.758400-1 0 0 0 04425 2151 4 4425 2 099999 4425 0 0 0 4.409600+4 9.508371+1 0 0 0 04425 3 4 1 0.000000+0-8.325700+5 0 0 1 714425 3 4 2 71 2 4425 3 4 3 8.413262+5 0.000000+0 8.660000+5 1.982000-1 9.000000+5 3.984000-14425 3 4 4 1.000000+6 7.442000-1 1.250000+6 1.029000+0 1.500000+6 1.121000+04425 3 4 5 1.534026+6 1.113378+0 1.951389+6 1.272022+0 2.000000+6 1.386540+04425 3 4 6 2.171399+6 1.388823+0 2.172379+6 1.389098+0 2.308223+6 1.428676+04425 3 4 7 2.487964+6 1.663148+0 2.500000+6 1.681600+0 2.551151+6 1.619646+04425 3 4 8 2.554991+6 1.616081+0 2.603193+6 1.587206+0 2.606123+6 1.586275+04425 3 4 9 2.615622+6 1.585830+0 2.677870+6 1.585947+0 2.728497+6 1.600803+04425 3 4 10 2.768615+6 1.620892+0 2.789229+6 1.638500+0 2.823223+6 1.669443+04425 3 4 11 2.881388+6 1.723760+0 2.922052+6 1.776756+0 2.928175+6 1.784770+04425 3 4 12 2.981430+6 1.873203+0 3.000000+6 1.904040+0 3.019223+6 1.890291+04425 3 4 13 3.027913+6 1.884981+0 3.092687+6 1.854175+0 3.108249+6 1.849020+04425 3 4 14 3.108896+6 1.848879+0 3.122700+6 1.846845+0 3.199994+6 1.846953+04425 3 4 15 3.243861+6 1.850401+0 3.266092+6 1.855873+0 3.295276+6 1.869603+04425 3 4 16 3.325612+6 1.890819+0 3.326218+6 1.891244+0 3.341497+6 1.902025+04425 3 4 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