JENDL-5 (Neutron sublibrary (activation cs)) Y - 90 0 0 0 0 3.909000+4 8.913481+1 0 0 6 13928 1451 1 0.000000+0 1.000000+0 0 0 0 63928 1451 2 1.000000+0 2.000000+7 0 0 10 53928 1451 3 2.936000+2 0.000000+0 4 0 391 273928 1451 4 39-Y - 90 JAEA EVAL-OCT09 A.Ichihara, K.Shibata, S.Kunieda+3928 1451 5 DIST-DEC21 20091201 3928 1451 6 ----JENDL-5 MATERIAL 3928 3928 1451 7 -----INCIDENT NEUTRON DATA 3928 1451 8 ------ENDF-6 FORMAT 3928 1451 9 3928 1451 10 History 3928 1451 11 09-10 Evaluated by A.Ichihara. 3928 1451 12 21-11 revised by O.Iwamoto 3928 1451 13 (MF8/MT4,16,17,22,28,32,102-107) JENDL/AD-2017 adopted 3928 1451 14 (MF9/MT102) JENDL/AD-2017 adopted 3928 1451 15 (MF10/MT4,16) JENDL/AD-2017 based 3928 1451 16 3928 1451 17 MF= 1 General information 3928 1451 18 MT=451 Descriptive data and directory 3928 1451 19 3928 1451 20 Cross sections were calculated with the POD code/1/ in 3928 1451 21 the neutron energy range from 200 eV to 20 MeV. 3928 1451 22 Elastic scattering cross section below 200 eV was estimated 3928 1451 23 with an effective scattering radius 6.74 fm of Y-89/2/. 3928 1451 24 Capture cross section at 0.0253 eV was estimated to be 3.25 b,3928 1451 25 which is half of a measured upper limit by Smith-Reeder/3/. 3928 1451 26 Capture cross section below 200 eV was obtained assuming 3928 1451 27 the 1/v relation. 3928 1451 28 3928 1451 29 MF= 2 Resonance parameters 3928 1451 30 MT=151 Unresolved resonance region : 200 eV - 200 keV 3928 1451 31 The unresolved resonance parameters were calculated using 3928 1451 32 the ASREP code/4/. 3928 1451 33 The parameters should be used only for self-shielding 3928 1451 34 calculation. 3928 1451 35 3928 1451 36 Thermal cross sections and resonance integrals at 300 K 3928 1451 37 ---------------------------------------------------------- 3928 1451 38 0.0253 eV res. integ. (*) 3928 1451 39 (barns) (barns) 3928 1451 40 ---------------------------------------------------------- 3928 1451 41 Total 9.0231E+00 3928 1451 42 Elastic 5.7427E+00 3928 1451 43 n,gamma 3.2513E+00 6.4125E+00 3928 1451 44 ---------------------------------------------------------- 3928 1451 45 (*) Integrated from 0.5 eV to 10 MeV. 3928 1451 46 3928 1451 47 MF= 3 Neutron cross sections 3928 1451 48 MT= 1 Total cross section 3928 1451 49 Calculated with POD code /1/. 3928 1451 50 3928 1451 51 MT= 2 Elastic scattering cross section 3928 1451 52 Calculated as (total - sum of partial cross sections). 3928 1451 53 3928 1451 54 MT= 3 Non-elastic cross section 3928 1451 55 Calculated as sum of partial cross sections. 3928 1451 56 3928 1451 57 MT= 4,51-91 (n,n') cross section 3928 1451 58 Calculated with POD code /1/. 3928 1451 59 3928 1451 60 MT= 16 (n,2n) cross section 3928 1451 61 Calculated with POD code /1/. 3928 1451 62 3928 1451 63 MT= 17 (n,3n) cross section 3928 1451 64 Calculated with POD code /1/. 3928 1451 65 3928 1451 66 MT= 22 (n,na) cross section 3928 1451 67 Calculated with POD code /1/. 3928 1451 68 3928 1451 69 MT= 28 (n,np) cross section 3928 1451 70 Calculated with POD code /1/. 3928 1451 71 3928 1451 72 MT= 32 (n,nd) cross section 3928 1451 73 Calculated with POD code /1/. 3928 1451 74 3928 1451 75 MT=102 Capture cross section 3928 1451 76 Calculated with POD code /1/. 3928 1451 77 3928 1451 78 MT=103 (n,p) cross section 3928 1451 79 Calculated with POD code /1/. 3928 1451 80 3928 1451 81 MT=104 (n,d) cross section 3928 1451 82 Calculated with POD code /1/. 3928 1451 83 3928 1451 84 MT=105 (n,t) cross section 3928 1451 85 Calculated with POD code /1/. 3928 1451 86 3928 1451 87 MT=106 (n,He3) cross section 3928 1451 88 Calculated with POD code /1/. 3928 1451 89 3928 1451 90 MT=107 (n,a) cross section 3928 1451 91 Calculated with POD code /1/. 3928 1451 92 3928 1451 93 MT=203 (n,xp) cross section 3928 1451 94 Calculated with POD code /1/. 3928 1451 95 3928 1451 96 MT=204 (n,xd) cross section 3928 1451 97 Calculated with POD code /1/. 3928 1451 98 3928 1451 99 MT=205 (n,xt) cross section 3928 1451 100 Calculated with POD code /1/. 3928 1451 101 3928 1451 102 MT=206 (n,xHe3) cross section 3928 1451 103 Calculated with POD code /1/. 3928 1451 104 3928 1451 105 MT=207 (n,xa) cross section 3928 1451 106 Calculated with POD code /1/. 3928 1451 107 3928 1451 108 MF= 4 Angular distributions of emitted neutrons 3928 1451 109 MT= 2 Elastic scattering 3928 1451 110 Calculated with POD code /1/. 3928 1451 111 3928 1451 112 MF= 6 Energy-angle distributions of emitted particles 3928 1451 113 MT= 16 (n,2n) reaction 3928 1451 114 Neutron spectra calculated with POD/1/. 3928 1451 115 3928 1451 116 MT= 17 (n,3n) reaction 3928 1451 117 Neutron spectra calculated with POD/1/. 3928 1451 118 3928 1451 119 MT= 22 (n,na) reaction 3928 1451 120 Neutron spectra calculated with POD/1/. 3928 1451 121 3928 1451 122 MT= 28 (n,np) reaction 3928 1451 123 Neutron spectra calculated with POD/1/. 3928 1451 124 3928 1451 125 MT= 32 (n,nd) reaction 3928 1451 126 Neutron spectra calculated with POD/1/. 3928 1451 127 3928 1451 128 MT= 51 (n,n') reaction 3928 1451 129 Neutron angular distributions calculated with POD/1/. 3928 1451 130 3928 1451 131 MT= 52 (n,n') reaction 3928 1451 132 Neutron angular distributions calculated with POD/1/. 3928 1451 133 3928 1451 134 MT= 53 (n,n') reaction 3928 1451 135 Neutron angular distributions calculated with POD/1/. 3928 1451 136 3928 1451 137 MT= 54 (n,n') reaction 3928 1451 138 Neutron angular distributions calculated with POD/1/. 3928 1451 139 3928 1451 140 MT= 55 (n,n') reaction 3928 1451 141 Neutron angular distributions calculated with POD/1/. 3928 1451 142 3928 1451 143 MT= 56 (n,n') reaction 3928 1451 144 Neutron angular distributions calculated with POD/1/. 3928 1451 145 3928 1451 146 MT= 57 (n,n') reaction 3928 1451 147 Neutron angular distributions calculated with POD/1/. 3928 1451 148 3928 1451 149 MT= 58 (n,n') reaction 3928 1451 150 Neutron angular distributions calculated with POD/1/. 3928 1451 151 3928 1451 152 MT= 59 (n,n') reaction 3928 1451 153 Neutron angular distributions calculated with POD/1/. 3928 1451 154 3928 1451 155 MT= 60 (n,n') reaction 3928 1451 156 Neutron angular distributions calculated with POD/1/. 3928 1451 157 3928 1451 158 MT= 61 (n,n') reaction 3928 1451 159 Neutron angular distributions calculated with POD/1/. 3928 1451 160 3928 1451 161 MT= 62 (n,n') reaction 3928 1451 162 Neutron angular distributions calculated with POD/1/. 3928 1451 163 3928 1451 164 MT= 63 (n,n') reaction 3928 1451 165 Neutron angular distributions calculated with POD/1/. 3928 1451 166 3928 1451 167 MT= 64 (n,n') reaction 3928 1451 168 Neutron angular distributions calculated with POD/1/. 3928 1451 169 3928 1451 170 MT= 65 (n,n') reaction 3928 1451 171 Neutron angular distributions calculated with POD/1/. 3928 1451 172 3928 1451 173 MT= 66 (n,n') reaction 3928 1451 174 Neutron angular distributions calculated with POD/1/. 3928 1451 175 3928 1451 176 MT= 67 (n,n') reaction 3928 1451 177 Neutron angular distributions calculated with POD/1/. 3928 1451 178 3928 1451 179 MT= 68 (n,n') reaction 3928 1451 180 Neutron angular distributions calculated with POD/1/. 3928 1451 181 3928 1451 182 MT= 69 (n,n') reaction 3928 1451 183 Neutron angular distributions calculated with POD/1/. 3928 1451 184 3928 1451 185 MT= 70 (n,n') reaction 3928 1451 186 Neutron angular distributions calculated with POD/1/. 3928 1451 187 3928 1451 188 MT= 71 (n,n') reaction 3928 1451 189 Neutron angular distributions calculated with POD/1/. 3928 1451 190 3928 1451 191 MT= 72 (n,n') reaction 3928 1451 192 Neutron angular distributions calculated with POD/1/. 3928 1451 193 3928 1451 194 MT= 73 (n,n') reaction 3928 1451 195 Neutron angular distributions calculated with POD/1/. 3928 1451 196 3928 1451 197 MT= 74 (n,n') reaction 3928 1451 198 Neutron angular distributions calculated with POD/1/. 3928 1451 199 3928 1451 200 MT= 75 (n,n') reaction 3928 1451 201 Neutron angular distributions calculated with POD/1/. 3928 1451 202 3928 1451 203 MT= 76 (n,n') reaction 3928 1451 204 Neutron angular distributions calculated with POD/1/. 3928 1451 205 3928 1451 206 MT= 77 (n,n') reaction 3928 1451 207 Neutron angular distributions calculated with POD/1/. 3928 1451 208 3928 1451 209 MT= 78 (n,n') reaction 3928 1451 210 Neutron angular distributions calculated with POD/1/. 3928 1451 211 3928 1451 212 MT= 79 (n,n') reaction 3928 1451 213 Neutron angular distributions calculated with POD/1/. 3928 1451 214 3928 1451 215 MT= 80 (n,n') reaction 3928 1451 216 Neutron angular distributions calculated with POD/1/. 3928 1451 217 3928 1451 218 MT= 81 (n,n') reaction 3928 1451 219 Neutron angular distributions calculated with POD/1/. 3928 1451 220 3928 1451 221 MT= 82 (n,n') reaction 3928 1451 222 Neutron angular distributions calculated with POD/1/. 3928 1451 223 3928 1451 224 MT= 83 (n,n') reaction 3928 1451 225 Neutron angular distributions calculated with POD/1/. 3928 1451 226 3928 1451 227 MT= 91 (n,n') reaction 3928 1451 228 Neutron spectra calculated with POD/1/. 3928 1451 229 3928 1451 230 MT= 203 (n,xp) reaction 3928 1451 231 Proton spectra calculated with POD/1/. 3928 1451 232 3928 1451 233 MT= 204 (n,xd) reaction 3928 1451 234 Deuteron spectra calculated with POD/1/. 3928 1451 235 3928 1451 236 MT= 205 (n,xt) reaction 3928 1451 237 Triton spectra calculated with POD/1/. 3928 1451 238 3928 1451 239 MT= 206 (n,xHe3) reaction 3928 1451 240 He3 spectra calculated with POD/1/. 3928 1451 241 3928 1451 242 MT= 207 (n,xa) reaction 3928 1451 243 Alpha spectra calculated with POD/1/. 3928 1451 244 3928 1451 245 MF=12 Gamma-ray multiplicities 3928 1451 246 MT= 3 Non-elastic gamma emission 3928 1451 247 Calculated with POD code /1/. 3928 1451 248 3928 1451 249 MF=14 Gamma-ray angular distributions 3928 1451 250 MT= 3 Non-elastic gamma emission 3928 1451 251 Assumed to be isotropic. 3928 1451 252 3928 1451 253 MF=15 Gamma-ray spectra 3928 1451 254 MT= 3 Non-elastic gamma emission 3928 1451 255 Calculated with POD code /1/. 3928 1451 256 3928 1451 257 3928 1451 258 3928 1451 259 *************************************************************** 3928 1451 260 * Nuclear Model Calculations with POD Code /1/ * 3928 1451 261 *************************************************************** 3928 1451 262 1. Theoretical models 3928 1451 263 The POD code is based on the spherical optical model, the 3928 1451 264 distorted-wave Born approximation (DWBA), one-component exciton 3928 1451 265 preequilibrium model, and the Hauser-Feshbach-Moldauer statis- 3928 1451 266 tical model. With the preequilibrim model, semi-empirical 3928 1451 267 pickup and knockout process can be taken into account for 3928 1451 268 composite-particle emission. The gamma-ray emission from the 3928 1451 269 compound nucleus can be calculated within the framework of the 3928 1451 270 exciton model. The code is capable of reading in particle 3928 1451 271 transmission coefficients calculated by separate spherical or 3928 1451 272 coupled-channel optical model code. 3928 1451 273 3928 1451 274 2. Optical model parameters 3928 1451 275 Neutrons: 3928 1451 276 Koning and Delaroche /5/ 3928 1451 277 Protons: 3928 1451 278 Koning and Delaroche /5/ 3928 1451 279 The radius parameter r_V = 1.25 fm was used in the calculation. 3928 1451 280 Deuterons: 3928 1451 281 Lohr and Haeberli /6/ 3928 1451 282 Tritons: 3928 1451 283 Becchetti and Greenlees /7/ 3928 1451 284 He-3: 3928 1451 285 Becchetti and Greenlees /7/ 3928 1451 286 Alphas: 3928 1451 287 Lemos /8/ potentials modified by Arthur and Young /9/. 3928 1451 288 The radius parameters r_V = r_I = 1.40 fm were used in the 3928 1451 289 calculation. 3928 1451 290 3928 1451 291 3. Level scheme of Y - 90 3928 1451 292 Nuclear discrete levels were obtained from RIPL-2/10/. 3928 1451 293 ------------------------- 3928 1451 294 No. Ex(MeV) J PI 3928 1451 295 ------------------------- 3928 1451 296 0 0.00000 2 - 3928 1451 297 1 0.20253 3 - 3928 1451 298 2 0.68167 7 + 3928 1451 299 3 0.77677 2 + 3928 1451 300 4 0.95367 3 + 3928 1451 301 5 1.04751 6 + 3928 1451 302 6 1.18991 7 - 3928 1451 303 7 1.21169 1 - 3928 1451 304 8 1.29820 5 + 3928 1451 305 9 1.37125 1 - 3928 1451 306 10 1.41666 0 + 3928 1451 307 11 1.57177 1 - 3928 1451 308 12 1.64111 3 - 3928 1451 309 13 1.76110 3 - 3928 1451 310 14 1.81170 3 - 3928 1451 311 15 1.81519 1 + 3928 1451 312 16 1.96090 4 + 3928 1451 313 17 2.00317 7 - 3928 1451 314 18 2.03000 4 + 3928 1451 315 19 2.08910 6 + 3928 1451 316 20 2.18496 3 + 3928 1451 317 21 2.21668 8 + 3928 1451 318 22 2.24090 4 + 3928 1451 319 23 2.24461 2 + 3928 1451 320 24 2.31300 1 + 3928 1451 321 25 2.32426 3 + 3928 1451 322 26 2.36613 1 - 3928 1451 323 27 2.45519 4 + 3928 1451 324 28 2.47420 2 - 3928 1451 325 29 2.50473 0 + 3928 1451 326 30 2.51700 6 + 3928 1451 327 31 2.56581 2 - 3928 1451 328 32 2.58969 2 + 3928 1451 329 33 2.62380 2 - 3928 1451 330 ------------------------- 3928 1451 331 Levels above 2.63380 MeV are assumed to be continuous. 3928 1451 332 3928 1451 333 4. Level density parameters 3928 1451 334 Energy-dependent parameters of Mengoni-Nakajima /11/ were used 3928 1451 335 --------------------------------------------------- 3928 1451 336 Nuclei a* Pair T E0 Ematch Elv_max 3928 1451 337 1/MeV MeV MeV MeV MeV MeV 3928 1451 338 --------------------------------------------------- 3928 1451 339 Y - 91 11.338 1.258 0.772 0.115 5.977 2.689 3928 1451 340 Y - 90 10.454 0.000 0.865 -0.779 4.677 2.624 3928 1451 341 Y - 89 11.127 1.272 0.682 1.455 3.665 4.023 3928 1451 342 Y - 88 11.494 0.000 0.820 -1.352 5.191 1.596 3928 1451 343 Sr- 90 11.748 2.530 0.778 1.141 7.584 3.627 3928 1451 344 Sr- 89 10.953 1.272 0.720 1.044 4.474 4.050 3928 1451 345 Sr- 88 11.473 2.558 0.785 1.929 6.625 5.199 3928 1451 346 Rb- 88 10.411 0.000 0.994 -2.333 7.292 1.964 3928 1451 347 Rb- 87 10.916 1.286 0.895 -0.274 7.103 3.099 3928 1451 348 Rb- 86 9.930 0.000 0.984 -2.108 6.936 2.025 3928 1451 349 --------------------------------------------------- 3928 1451 350 3928 1451 351 5. Gamma-ray strength functions 3928 1451 352 M1, E2: Standard Lorentzian (SLO) 3928 1451 353 E1 : Standard Lorentzian (SLO) /12/ 3928 1451 354 The position and width parameters in the E1 3928 1451 355 radiation were taken from the tabulation of 3928 1451 356 Dietrich and Berman/13/. 3928 1451 357 3928 1451 358 6. Preequilibrium process 3928 1451 359 Preequilibrium is on for n, p, d, t, He-3, and alpha. 3928 1451 360 3928 1451 361 The single particle state density parameters were 3928 1451 362 6.958, 6.923, 7.202, 6.359, 5.500, 6.383, 6.188 (MeV^-1) 3928 1451 363 for Y-91, Y-90, Sr-90, Rb-87, Sr-89, Sr-88, and Rb-88. 3928 1451 364 3928 1451 365 Effects of the particle pickup (and knockout for alpha) were 3928 1451 366 estimated using the semi-empirical formulas by Kalbach/14/. 3928 1451 367 These components were multiplied by a factor of two and 3928 1451 368 added to the statistical model calculation. 3928 1451 369 3928 1451 370 Preequilibrium capture is on (the parameters were obtained 3928 1451 371 from /13/). 3928 1451 372 3928 1451 373 References 3928 1451 374 1) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 3928 1451 375 2) S.F.Mughabghab, "Atlas of Neutron Resonances," Elsevier 3928 1451 376 (2006). 3928 1451 377 3) R.R.Smith, S.D.Reeder, J. Chem. Phys. 23, 2108 (1955). 3928 1451 378 4) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999) 3928 1451 379 [in Japanese]. 3928 1451 380 5) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 3928 1451 381 6) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 3928 1451 382 7) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization 3928 1451 383 Phenomena in Nuclear Reactions," p.682, The University 3928 1451 384 of Wisconsin Press (1971). 3928 1451 385 8) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 3928 1451 386 9) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 3928 1451 387 10) T.Belgya et al., IAEA-TECDOC-1506 (2006). 3928 1451 388 11) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 3928 1451 389 (1994). 3928 1451 390 12) M.Brink, Ph.D thesis, Oxford University, 1955. 3928 1451 391 13) S.S.Dietrich, B.L.Berman, Atom. Data Nucl. Data Tables, 3928 1451 392 38, 199 (1988). 3928 1451 393 14) C.Kalbach, Z. Phys. A283, 401 (1977). 3928 1451 394 3928 1451 395 1 451 422 13928 1451 396 2 151 4 13928 1451 397 3 4 30 13928 1451 398 3 17 4 13928 1451 399 3 22 7 13928 1451 400 3 28 8 13928 1451 401 3 32 6 13928 1451 402 3 103 15 13928 1451 403 3 104 8 13928 1451 404 3 105 8 13928 1451 405 3 106 6 13928 1451 406 3 107 14 13928 1451 407 8 4 2 13928 1451 408 8 16 3 13928 1451 409 8 17 2 13928 1451 410 8 22 2 13928 1451 411 8 28 2 13928 1451 412 8 32 2 13928 1451 413 8 102 3 03928 1451 414 8 103 2 13928 1451 415 8 104 2 13928 1451 416 8 105 2 13928 1451 417 8 106 2 13928 1451 418 8 107 2 13928 1451 419 10 4 17 13928 1451 420 10 16 15 13928 1451 421 10 102 257 03928 1451 422 3928 1 099999 3928 0 0 0 3.909000+4 8.913481+1 0 0 1 03928 2151 1 3.909000+4 1.000000+0 0 0 1 03928 2151 2 2.000000+2 2.000000+5 0 0 0 03928 2151 3 2.000000+0 6.489700-1 0 0 0 03928 2151 4 3928 2 099999 3928 0 0 0 3.909000+4 8.913481+1 0 0 0 03928 3 4 1 0.000000+0-2.025300+5 0 0 1 793928 3 4 2 79 2 3928 3 4 3 2.048022+5 0.000000+0 2.500000+5 3.166000-1 3.000000+5 5.709000-13928 3 4 4 3.500000+5 7.406000-1 4.000000+5 8.511000-1 5.000000+5 9.553000-13928 3 4 5 6.000000+5 9.804000-1 6.893176+5 9.705751-1 7.000000+5 9.725300-13928 3 4 6 7.854846+5 9.455750-1 8.000000+5 9.737280-1 9.000000+5 1.039667+03928 3 4 7 9.643692+5 1.042224+0 1.000000+6 1.092770+0 1.059262+6 1.110000+03928 3 4 8 1.200000+6 1.183000+0 1.203260+6 1.182320+0 1.225284+6 1.180802+03928 3 4 9 1.312764+6 1.233004+0 1.386634+6 1.303876+0 1.400000+6 1.325656+03928 3 4 10 1.432553+6 1.344825+0 1.589404+6 1.454108+0 1.600000+6 1.468694+03928 3 4 11 1.659522+6 1.490268+0 1.700000+6 1.531740+0 1.780858+6 1.579923+03928 3 4 12 1.800000+6 1.603760+0 1.832025+6 1.613819+0 1.835555+6 1.616808+03928 3 4 13 1.900000+6 1.686440+0 1.982899+6 1.735276+0 2.000000+6 1.756020+03928 3 4 14 2.025643+6 1.762444+0 2.052774+6 1.772627+0 2.100000+6 1.805752+03928 3 4 15 2.112538+6 1.808915+0 2.200000+6 1.841510+0 2.209473+6 1.839808+03928 3 4 16 2.241549+6 1.841470+0 2.266041+6 1.844523+0 2.269792+6 1.846182+03928 3 4 17 2.300000+6 1.868949+0 2.338949+6 1.867197+0 2.350336+6 1.868481+03928 3 4 18 2.392676+6 1.883807+0 2.400000+6 1.891214+0 2.482735+6 1.899759+03928 3 4 19 2.500000+6 1.909203+0 2.501958+6 1.908771+0 2.532830+6 1.908831+03928 3 4 20 2.545238+6 1.909879+0 2.594596+6 1.920196+0 2.600000+6 1.925954+03928 3 4 21 2.618744+6 1.927530+0 2.653236+6 1.934097+0 2.663349+6 1.937920+03928 3 4 22 2.800000+6 2.041258+0 3.000000+6 2.056425+0 3.500000+6 2.037785+03928 3 4 23 4.000000+6 1.978917+0 4.500000+6 1.921544+0 5.000000+6 1.874501+03928 3 4 24 5.500000+6 1.850930+0 6.000000+6 1.840835+0 7.000000+6 1.837334+03928 3 4 25 8.000000+6 1.592127+0 9.000000+6 1.140019+0 1.000000+7 8.266115-13928 3 4 26 1.100000+7 6.220513-1 1.200000+7 4.996330-1 1.300000+7 4.250683-13928 3 4 27 1.400000+7 3.693540-1 1.500000+7 3.270938-1 1.600000+7 2.955741-13928 3 4 28 1.700000+7 2.683088-1 1.800000+7 2.422952-1 1.900000+7 2.266000-13928 3 4 29 2.000000+7 2.096340-1 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