JENDL-5 (Neutron sublibrary (activation cs)) Ru-103 0 0 0 0 4.410300+4 1.020223+2 0 0 6 14446 1451 1 0.000000+0 1.000000+0 0 0 0 64446 1451 2 1.000000+0 2.000000+7 0 0 10 54446 1451 3 2.936000+2 0.000000+0 4 0 434 264446 1451 4 44-Ru-103 JAEA EVAL-JUL12 K.Shibata 4446 1451 5 JNST 50, 1177 (2013) DIST-DEC21 20180517 4446 1451 6 ----JENDL-5 MATERIAL 4446 4446 1451 7 -----INCIDENT NEUTRON DATA 4446 1451 8 ------ENDF-6 FORMAT 4446 1451 9 4446 1451 10 History 4446 1451 11 12-07 The fast neutron cross sections were evaluated by 4446 1451 12 K. Shibata (JAEA) /1/ using the POD code. 4446 1451 13 13-04 The comment data were corrected. 4446 1451 14 18-05 Activation cross sections added by K.Shibata. 4446 1451 15 21-11 revised by O.Iwamoto 4446 1451 16 (MF8/MT4) added 4446 1451 17 21-11 above 20 MeV, JENDL/ImPACT-2018 merged by O.Iwamoto 4446 1451 18 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 4446 1451 19 4446 1451 20 4446 1451 21 MF= 1 General information 4446 1451 22 MT=451 Descriptive data and directory 4446 1451 23 4446 1451 24 MF= 2 Resonance parameters 4446 1451 25 MT=151 Resolved and unresolved resonance parameters 4446 1451 26 Resolved Resonance Parameters (MLBW; below 50 eV) 4446 1451 27 The resonance parameters of 8 levels up to 330 eV were 4446 1451 28 obtained by Anufriev et al./2/ Their parameters were 4446 1451 29 adopted. In addition, a negative resonance was assumed at 4446 1451 30 -3.0 eV and its parameters were determined so that the 4446 1451 31 capture cross section at 0.0253 eV was about 10 b. 4446 1451 32 An upper bounday of the resolved resonance region was set at4446 1451 33 50 eV, because level missing was obvious above this energy. 4446 1451 34 Unresolved resonance region: 50 eV - 100 keV 4446 1451 35 The parameters were obtained by fitting to the calculated 4446 1451 36 total and capture cross sections. The unresolved resonance 4446 1451 37 parameters obtained should be used only for self-shielding 4446 1451 38 calculation. URP's were re-calculated by fitting to the 4446 1451 39 total and capture cross sections calculated by POD /3/. 4446 1451 40 4446 1451 41 Thermal cross sections and resonance integrals at 300 K 4446 1451 42 ---------------------------------------------------------- 4446 1451 43 0.0253 eV res. integ. (*) 4446 1451 44 (barns) (barns) 4446 1451 45 ---------------------------------------------------------- 4446 1451 46 Total 1.4637E+01 4446 1451 47 Elastic 5.0826E+00 4446 1451 48 n,gamma 9.5545E+00 7.1292E+01 4446 1451 49 ---------------------------------------------------------- 4446 1451 50 (*) Integrated from 0.5 eV to 10 MeV. 4446 1451 51 4446 1451 52 MF= 3 Neutron cross sections 4446 1451 53 MT= 1 Total cross section 4446 1451 54 Calculated with POD code /3/. 4446 1451 55 4446 1451 56 MT= 2 Elastic scattering cross section 4446 1451 57 The cross section was obtained by subtracting the non-elastic 4446 1451 58 cross section from the total cross section. 4446 1451 59 4446 1451 60 MT= 3 Non-elastic cross section 4446 1451 61 Sum of partial non-elastic cross sections. 4446 1451 62 4446 1451 63 MT= 4,51-91 (n,n') cross section 4446 1451 64 Calculated with POD code /3/. 4446 1451 65 4446 1451 66 MT= 16 (n,2n) cross section 4446 1451 67 Calculated with POD code /3/. 4446 1451 68 4446 1451 69 MT= 17 (n,3n) cross section 4446 1451 70 Calculated with POD code /3/. 4446 1451 71 4446 1451 72 MT= 22 (n,na) cross section 4446 1451 73 Calculated with POD code /3/. 4446 1451 74 4446 1451 75 MT= 28 (n,np) cross section 4446 1451 76 Calculated with POD code /3/. 4446 1451 77 4446 1451 78 MT= 32 (n,nd) cross section 4446 1451 79 Calculated with POD code /3/. 4446 1451 80 4446 1451 81 MT=102 Capture cross section 4446 1451 82 Calculated with POD code /3/. 4446 1451 83 4446 1451 84 MT=103 (n,p) cross section 4446 1451 85 Calculated with POD code /3/. 4446 1451 86 4446 1451 87 MT=104 (n,d) cross section 4446 1451 88 Calculated with POD code /3/. 4446 1451 89 4446 1451 90 MT=105 (n,t) cross section 4446 1451 91 Calculated with POD code /3/. 4446 1451 92 4446 1451 93 MT=106 (n,He3) cross section 4446 1451 94 Calculated with POD code /3/. 4446 1451 95 4446 1451 96 MT=107 (n,a) cross section 4446 1451 97 Calculated with POD code /3/. 4446 1451 98 4446 1451 99 MT=203 (n,xp) cross section 4446 1451 100 Calculated with POD code /3/. 4446 1451 101 4446 1451 102 MT=204 (n,xd) cross section 4446 1451 103 Calculated with POD code /3/. 4446 1451 104 4446 1451 105 MT=205 (n,xt) cross section 4446 1451 106 Calculated with POD code /3/. 4446 1451 107 4446 1451 108 MT=206 (n,xHe3) cross section 4446 1451 109 Calculated with POD code /3/. 4446 1451 110 4446 1451 111 MT=207 (n,xa) cross section 4446 1451 112 Calculated with POD code /3/. 4446 1451 113 4446 1451 114 MF= 4 Angular distributions of emitted neutrons 4446 1451 115 MT= 2 Elastic scattering 4446 1451 116 Calculated with POD code /3/. 4446 1451 117 4446 1451 118 MF= 6 Energy-angle distributions of emitted particles 4446 1451 119 MT= 16 (n,2n) reaction 4446 1451 120 Neutron spectra calculated with POD/3/. 4446 1451 121 4446 1451 122 MT= 17 (n,3n) reaction 4446 1451 123 Neutron spectra calculated with POD/3/. 4446 1451 124 4446 1451 125 MT= 22 (n,na) reaction 4446 1451 126 Neutron spectra calculated with POD/3/. 4446 1451 127 4446 1451 128 MT= 28 (n,np) reaction 4446 1451 129 Neutron spectra calculated with POD/3/. 4446 1451 130 4446 1451 131 MT= 32 (n,nd) reaction 4446 1451 132 Neutron spectra calculated with POD/3/. 4446 1451 133 4446 1451 134 MT= 51 (n,n') reaction 4446 1451 135 Neutron angular distributions calculated with POD/3/. 4446 1451 136 4446 1451 137 MT= 52 (n,n') reaction 4446 1451 138 Neutron angular distributions calculated with POD/3/. 4446 1451 139 4446 1451 140 MT= 53 (n,n') reaction 4446 1451 141 Neutron angular distributions calculated with POD/3/. 4446 1451 142 4446 1451 143 MT= 54 (n,n') reaction 4446 1451 144 Neutron angular distributions calculated with POD/3/. 4446 1451 145 4446 1451 146 MT= 55 (n,n') reaction 4446 1451 147 Neutron angular distributions calculated with POD/3/. 4446 1451 148 4446 1451 149 MT= 56 (n,n') reaction 4446 1451 150 Neutron angular distributions calculated with POD/3/. 4446 1451 151 4446 1451 152 MT= 57 (n,n') reaction 4446 1451 153 Neutron angular distributions calculated with POD/3/. 4446 1451 154 4446 1451 155 MT= 58 (n,n') reaction 4446 1451 156 Neutron angular distributions calculated with POD/3/. 4446 1451 157 4446 1451 158 MT= 59 (n,n') reaction 4446 1451 159 Neutron angular distributions calculated with POD/3/. 4446 1451 160 4446 1451 161 MT= 60 (n,n') reaction 4446 1451 162 Neutron angular distributions calculated with POD/3/. 4446 1451 163 4446 1451 164 MT= 61 (n,n') reaction 4446 1451 165 Neutron angular distributions calculated with POD/3/. 4446 1451 166 4446 1451 167 MT= 62 (n,n') reaction 4446 1451 168 Neutron angular distributions calculated with POD/3/. 4446 1451 169 4446 1451 170 MT= 63 (n,n') reaction 4446 1451 171 Neutron angular distributions calculated with POD/3/. 4446 1451 172 4446 1451 173 MT= 64 (n,n') reaction 4446 1451 174 Neutron angular distributions calculated with POD/3/. 4446 1451 175 4446 1451 176 MT= 65 (n,n') reaction 4446 1451 177 Neutron angular distributions calculated with POD/3/. 4446 1451 178 4446 1451 179 MT= 66 (n,n') reaction 4446 1451 180 Neutron angular distributions calculated with POD/3/. 4446 1451 181 4446 1451 182 MT= 67 (n,n') reaction 4446 1451 183 Neutron angular distributions calculated with POD/3/. 4446 1451 184 4446 1451 185 MT= 68 (n,n') reaction 4446 1451 186 Neutron angular distributions calculated with POD/3/. 4446 1451 187 4446 1451 188 MT= 69 (n,n') reaction 4446 1451 189 Neutron angular distributions calculated with POD/3/. 4446 1451 190 4446 1451 191 MT= 70 (n,n') reaction 4446 1451 192 Neutron angular distributions calculated with POD/3/. 4446 1451 193 4446 1451 194 MT= 71 (n,n') reaction 4446 1451 195 Neutron angular distributions calculated with POD/3/. 4446 1451 196 4446 1451 197 MT= 72 (n,n') reaction 4446 1451 198 Neutron angular distributions calculated with POD/3/. 4446 1451 199 4446 1451 200 MT= 73 (n,n') reaction 4446 1451 201 Neutron angular distributions calculated with POD/3/. 4446 1451 202 4446 1451 203 MT= 74 (n,n') reaction 4446 1451 204 Neutron angular distributions calculated with POD/3/. 4446 1451 205 4446 1451 206 MT= 75 (n,n') reaction 4446 1451 207 Neutron angular distributions calculated with POD/3/. 4446 1451 208 4446 1451 209 MT= 76 (n,n') reaction 4446 1451 210 Neutron angular distributions calculated with POD/3/. 4446 1451 211 4446 1451 212 MT= 77 (n,n') reaction 4446 1451 213 Neutron angular distributions calculated with POD/3/. 4446 1451 214 4446 1451 215 MT= 78 (n,n') reaction 4446 1451 216 Neutron angular distributions calculated with POD/3/. 4446 1451 217 4446 1451 218 MT= 79 (n,n') reaction 4446 1451 219 Neutron angular distributions calculated with POD/3/. 4446 1451 220 4446 1451 221 MT= 80 (n,n') reaction 4446 1451 222 Neutron angular distributions calculated with POD/3/. 4446 1451 223 4446 1451 224 MT= 81 (n,n') reaction 4446 1451 225 Neutron angular distributions calculated with POD/3/. 4446 1451 226 4446 1451 227 MT= 82 (n,n') reaction 4446 1451 228 Neutron angular distributions calculated with POD/3/. 4446 1451 229 4446 1451 230 MT= 83 (n,n') reaction 4446 1451 231 Neutron angular distributions calculated with POD/3/. 4446 1451 232 4446 1451 233 MT= 84 (n,n') reaction 4446 1451 234 Neutron angular distributions calculated with POD/3/. 4446 1451 235 4446 1451 236 MT= 85 (n,n') reaction 4446 1451 237 Neutron angular distributions calculated with POD/3/. 4446 1451 238 4446 1451 239 MT= 86 (n,n') reaction 4446 1451 240 Neutron angular distributions calculated with POD/3/. 4446 1451 241 4446 1451 242 MT= 87 (n,n') reaction 4446 1451 243 Neutron angular distributions calculated with POD/3/. 4446 1451 244 4446 1451 245 MT= 88 (n,n') reaction 4446 1451 246 Neutron angular distributions calculated with POD/3/. 4446 1451 247 4446 1451 248 MT= 89 (n,n') reaction 4446 1451 249 Neutron angular distributions calculated with POD/3/. 4446 1451 250 4446 1451 251 MT= 90 (n,n') reaction 4446 1451 252 Neutron angular distributions calculated with POD/3/. 4446 1451 253 4446 1451 254 MT= 91 (n,n') reaction 4446 1451 255 Neutron spectra calculated with POD/3/. 4446 1451 256 4446 1451 257 MT= 203 (n,xp) reaction 4446 1451 258 Proton spectra calculated with POD/3/. 4446 1451 259 4446 1451 260 MT= 204 (n,xd) reaction 4446 1451 261 Deuteron spectra calculated with POD/3/. 4446 1451 262 4446 1451 263 MT= 205 (n,xt) reaction 4446 1451 264 Triton spectra calculated with POD/3/. 4446 1451 265 4446 1451 266 MT= 206 (n,xHe3) reaction 4446 1451 267 He3 spectra calculated with POD/3/. 4446 1451 268 4446 1451 269 MT= 207 (n,xa) reaction 4446 1451 270 Alpha spectra calculated with POD/3/. 4446 1451 271 4446 1451 272 MF= 8 Information on decay data 4446 1451 273 MT= 16 (n,2n) reaction 4446 1451 274 4446 1451 275 MT= 17 (n,3n) reaction 4446 1451 276 4446 1451 277 MT= 22 (n,na) reaction 4446 1451 278 4446 1451 279 MT= 28 (n,np) reaction 4446 1451 280 4446 1451 281 MT= 32 (n,nd) reaction 4446 1451 282 4446 1451 283 MT=102 (n,g) reaction 4446 1451 284 4446 1451 285 MT=103 (n,p) reaction 4446 1451 286 4446 1451 287 MT=104 (n,d) reaction 4446 1451 288 4446 1451 289 MT=105 (n,t) reaction 4446 1451 290 4446 1451 291 MT=106 (n,He3) reaction 4446 1451 292 4446 1451 293 MT=107 (n,a) reaction 4446 1451 294 4446 1451 295 MF=10 Nuclide production cross sections 4446 1451 296 MT= 28 Partial (n,np) reactions 4446 1451 297 Calculated with POD code /3/. 4446 1451 298 4446 1451 299 MT=104 Partial (n,d) reactions 4446 1451 300 Calculated with POD code /3/. 4446 1451 301 4446 1451 302 MF=12 Gamma-ray multiplicities 4446 1451 303 MT= 3 Non-elastic gamma emission 4446 1451 304 Calculated with POD code /3/. 4446 1451 305 4446 1451 306 MF=14 Gamma-ray angular distributions 4446 1451 307 MT= 3 Non-elastic gamma emission 4446 1451 308 Assumed to be isotropic. 4446 1451 309 4446 1451 310 MF=15 Gamma-ray spectra 4446 1451 311 MT= 3 Non-elastic gamma emission 4446 1451 312 Calculated with POD code /3/. 4446 1451 313 4446 1451 314 4446 1451 315 4446 1451 316 *************************************************************** 4446 1451 317 * Nuclear Model Calculations with POD Code /3/ * 4446 1451 318 *************************************************************** 4446 1451 319 1. Theoretical models 4446 1451 320 The POD code is based on the spherical optical model, the 4446 1451 321 distorted-wave Born approximaiton (DWBA), one-component exciton 4446 1451 322 preequilibrium model, and the Hauser-Feshbach-Moldauer statis- 4446 1451 323 tical model. With the preequilibrim model, semi-empirical 4446 1451 324 pickup and knockout process can be taken into account for 4446 1451 325 composite-particle emission. The gamma-ray emission from the 4446 1451 326 compound nucleus can be calculated within the framework of the 4446 1451 327 exciton model. The code is capable of reading in particle 4446 1451 328 transmission coefficients calculated by separate spherical or 4446 1451 329 coupled-channel optical model code. 4446 1451 330 4446 1451 331 2. Optical model parameters 4446 1451 332 Neutrons: 4446 1451 333 Coupled-channel optical model parameters /4/ 4446 1451 334 Protons: 4446 1451 335 Koning and Delaroche /5/ 4446 1451 336 Deuterons: 4446 1451 337 Lohr and Haeberli /6/ 4446 1451 338 Tritons: 4446 1451 339 Becchetti and Greenlees /7/ 4446 1451 340 He-3: 4446 1451 341 Becchetti and Greenlees /7/ 4446 1451 342 Alphas: 4446 1451 343 Lemos /8/ potentials modified by Arthur and Young /9/ 4446 1451 344 4446 1451 345 3. Level scheme of Ru-103 4446 1451 346 ------------------------- 4446 1451 347 No. Ex(MeV) J PI 4446 1451 348 ------------------------- 4446 1451 349 0 0.00000 3/2 + 4446 1451 350 1 0.00281 5/2 + 4446 1451 351 2* 0.13608 5/2 + 4446 1451 352 3 0.17426 1/2 + 4446 1451 353 4* 0.21356 7/2 + 4446 1451 354 5 0.23820 11/2 - 4446 1451 355 6 0.29748 7/2 - 4446 1451 356 7 0.29760 3/2 + 4446 1451 357 8 0.34638 3/2 + 4446 1451 358 9 0.40415 7/2 + 4446 1451 359 10 0.40608 5/2 + 4446 1451 360 11 0.43206 1/2 + 4446 1451 361 12 0.47590 3/2 - 4446 1451 362 13 0.50115 5/2 + 4446 1451 363 14 0.53540 5/2 + 4446 1451 364 15 0.54821 1/2 + 4446 1451 365 16 0.55458 1/2 + 4446 1451 366 17 0.55770 9/2 + 4446 1451 367 18 0.56287 5/2 + 4446 1451 368 19 0.56817 3/2 - 4446 1451 369 20 0.59197 5/2 + 4446 1451 370 21 0.62200 5/2 + 4446 1451 371 22 0.65370 15/2 - 4446 1451 372 23 0.66155 3/2 + 4446 1451 373 24 0.69720 7/2 + 4446 1451 374 25 0.73520 5/2 + 4446 1451 375 26 0.73689 1/2 + 4446 1451 376 27 0.74880 5/2 + 4446 1451 377 28 0.77100 7/2 + 4446 1451 378 29 0.77410 11/2 + 4446 1451 379 30 0.77477 5/2 + 4446 1451 380 31 0.85500 5/2 - 4446 1451 381 32 0.87371 3/2 + 4446 1451 382 33 0.90305 5/2 - 4446 1451 383 34 0.90536 3/2 + 4446 1451 384 35 0.90764 5/2 + 4446 1451 385 36 0.91160 7/2 + 4446 1451 386 37 0.92724 1/2 + 4446 1451 387 38 0.93130 5/2 + 4446 1451 388 39 0.94050 7/2 - 4446 1451 389 40 0.95440 3/2 - 4446 1451 390 ------------------------- 4446 1451 391 Levels above 0.96440 MeV are assumed to be continuous. 4446 1451 392 The symbol (*) stands for the excited level involved in the 4446 1451 393 coupled-channel calculation. 4446 1451 394 4446 1451 395 4. Level density parameters 4446 1451 396 Energy-dependent parameters of Mengoni-Nakajima /10/ were used 4446 1451 397 ---------------------------------------------------------- 4446 1451 398 Nuclei a* Pair Esh T E0 Ematch Elv_max 4446 1451 399 1/MeV MeV MeV MeV MeV MeV MeV 4446 1451 400 ---------------------------------------------------------- 4446 1451 401 Ru-104 13.272 2.353 3.632 0.656 0.316 7.723 2.619 4446 1451 402 Ru-103 13.854 1.182 3.548 0.717 -1.842 8.034 0.954 4446 1451 403 Ru-102 13.056 2.376 2.653 0.711 0.144 8.244 2.460 4446 1451 404 Ru-101 13.639 1.194 2.251 0.781 -2.049 8.618 0.742 4446 1451 405 Tc-103 12.611 1.182 4.679 0.684 -1.198 7.098 0.692 4446 1451 406 Tc-102 13.006 0.000 4.218 0.592 -1.461 4.334 0.267 4446 1451 407 Tc-101 12.403 1.194 3.830 0.737 -1.432 7.661 1.271 4446 1451 408 Mo-101 14.580 1.194 4.672 0.597 -1.025 6.467 0.984 4446 1451 409 Mo-100 12.840 2.400 3.838 0.682 0.173 8.102 2.339 4446 1451 410 Mo- 99 13.082 1.206 3.377 0.716 -1.379 7.501 1.405 4446 1451 411 ---------------------------------------------------------- 4446 1451 412 4446 1451 413 5. Gamma-ray strength functions 4446 1451 414 M1, E2: Standard Lorentzian (SLO) 4446 1451 415 E1 : Modified Lorentzian (MLO) /11/ 4446 1451 416 4446 1451 417 6. Preequilibrium process 4446 1451 418 Preequilibrium is on for n, p, d, t, He-3, and alpha. 4446 1451 419 Preequilibrium capture is on. 4446 1451 420 4446 1451 421 References 4446 1451 422 1) K.Shibata, J. Nucl. Sci. Technol., 50, 1177 (2013). 4446 1451 423 2) V.A.Anufriev et al., 1980 Kiev, Vol.2, p.156 (1980). 4446 1451 424 3) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 4446 1451 425 4) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 4446 1451 426 5) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 4446 1451 427 6) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 4446 1451 428 7) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization 4446 1451 429 Phenomena in Nuclear Reactions," p.682, The University 4446 1451 430 of Wisconsin Press (1971). 4446 1451 431 8) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 4446 1451 432 9) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 4446 1451 433 10) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 4446 1451 434 (1994). 4446 1451 435 11) V.A.Plujko et al., J. Nucl. Sci. Technol. Suppl. 2, 811 4446 1451 436 (2002). 4446 1451 437 4446 1451 438 1 451 464 14446 1451 439 2 151 4 14446 1451 440 3 4 36 14446 1451 441 3 16 10 14446 1451 442 3 17 5 14446 1451 443 3 22 8 14446 1451 444 3 32 5 14446 1451 445 3 102 480 14446 1451 446 3 103 12 14446 1451 447 3 105 8 14446 1451 448 3 106 5 14446 1451 449 3 107 13 14446 1451 450 8 4 2 14446 1451 451 8 16 2 14446 1451 452 8 17 2 14446 1451 453 8 22 2 14446 1451 454 8 28 3 14446 1451 455 8 32 2 14446 1451 456 8 102 2 14446 1451 457 8 103 2 14446 1451 458 8 104 3 14446 1451 459 8 105 2 14446 1451 460 8 106 2 14446 1451 461 8 107 2 14446 1451 462 10 28 13 14446 1451 463 10 104 15 14446 1451 464 4446 1 099999 4446 0 0 0 4.410300+4 1.020223+2 0 0 1 04446 2151 1 4.410300+4 1.000000+0 0 0 1 04446 2151 2 1.000000-5 5.000000+1 0 0 0 04446 2151 3 1.500000+0 6.500000-1 0 0 0 04446 2151 4 4446 2 099999 4446 0 0 0 4.410300+4 1.020223+2 0 0 0 04446 3 4 1 0.000000+0-2.810000+3 0 0 1 974446 3 4 2 97 2 4446 3 4 3 2.837543+3 0.000000+0 3.000000+3 2.004000-1 4.000000+3 3.473000-14446 3 4 4 5.000000+3 3.699000-1 6.000000+3 3.733000-1 7.000000+3 3.716000-14446 3 4 5 8.000000+3 3.690000-1 9.000000+3 3.666000-1 1.000000+4 3.663000-14446 3 4 6 2.000000+4 3.792000-1 3.000000+4 4.139000-1 4.000000+4 4.503000-14446 3 4 7 5.000000+4 4.844000-1 6.000000+4 5.158000-1 7.000000+4 5.446000-14446 3 4 8 8.000000+4 5.712000-1 9.000000+4 5.958000-1 1.000000+5 6.190000-14446 3 4 9 1.374128+5 6.527838-1 1.759681+5 8.308251-1 2.000000+5 1.000520+04446 3 4 10 2.156533+5 1.041278+0 2.405348+5 1.141670+0 3.000000+5 1.386494+04446 3 4 11 3.003958+5 1.386737+0 3.005170+5 1.386897+0 3.497751+5 1.530524+04446 3 4 12 4.000000+5 1.756740+0 4.081114+5 1.761310+0 4.100603+5 1.763481+04446 3 4 13 4.362950+5 1.816720+0 4.805647+5 1.931805+0 5.000000+5 2.005270+04446 3 4 14 5.060622+5 2.005734+0 5.406479+5 2.029532+0 5.535834+5 2.045973+04446 3 4 15 5.600159+5 2.056506+0 5.631665+5 2.062821+0 5.683871+5 2.074137+04446 3 4 16 5.737391+5 2.088809+0 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