JENDL-5 (Neutron sublibrary (activation cs)) Sb-124 0 0 0 0 5.112400+4 1.228415+2 0 0 6 15134 1451 1 0.000000+0 1.000000+0 0 0 0 65134 1451 2 1.000000+0 2.000000+7 0 0 10 55134 1451 3 2.936000+2 0.000000+0 4 0 414 275134 1451 4 51-Sb-124 JAEA EVAL-MAR13 K.Shibata 5134 1451 5 JNST 51, 425 (2014) DIST-DEC21 20180518 5134 1451 6 ----JENDL-5 MATERIAL 5134 5134 1451 7 -----INCIDENT NEUTRON DATA 5134 1451 8 ------ENDF-6 FORMAT 5134 1451 9 5134 1451 10 History 5134 1451 11 13-03 Re-evaluation was performed by K. Shibata (JAEA)./1/ 5134 1451 12 5134 1451 13 MF= 1 General information 5134 1451 14 MT=451 Descriptive data and directory 5134 1451 15 5134 1451 16 MF= 2 Resonance parameters 5134 1451 17 MT=151 Resolved and unresolved resonance parameters 5134 1451 18 No resolved resonance parameters 5134 1451 19 5134 1451 20 Unresolved resonance region: 10 eV - 100 keV 5134 1451 21 The parameters were obtained by fitting to the evaluated 5134 1451 22 total and capture cross sections. The unresolved resonance 5134 1451 23 parameters obtained should be used only for self-shielding 5134 1451 24 calculation. 5134 1451 25 5134 1451 26 Thermal cross sections and resonance integrals at 300 K 5134 1451 27 ---------------------------------------------------------- 5134 1451 28 0.0253 eV res. integ. (*) 5134 1451 29 (barns) (barns) 5134 1451 30 ---------------------------------------------------------- 5134 1451 31 Total 2.1096E+01 5134 1451 32 Elastic 3.6548E+00 5134 1451 33 n,gamma 1.7408E+01 1.4987E+02 5134 1451 34 ---------------------------------------------------------- 5134 1451 35 (*) Integrated from 0.5 eV to 10 MeV. 5134 1451 36 5134 1451 37 MF= 3 Neutron cross sections 5134 1451 38 MT= 1 Total cross section 5134 1451 39 Calculated with POD code /2/. 5134 1451 40 5134 1451 41 MT= 2 Elastic scattering cross section 5134 1451 42 The cross section was obtained by subtracting the non-elastic 5134 1451 43 cross section from the total cross section. Below 10 eV, the 5134 1451 44 cross section was set to 3.63956 barns. 5134 1451 45 5134 1451 46 MT= 3 Non-elastic cross section 5134 1451 47 Sum of partial non-elastic cross sections. 5134 1451 48 5134 1451 49 MT= 4,51-91 (n,n') cross section 5134 1451 50 Calculated with POD code /2/. 5134 1451 51 5134 1451 52 MT= 16 (n,2n) cross section 5134 1451 53 Calculated with POD code /2/. 5134 1451 54 5134 1451 55 MT= 17 (n,3n) cross section 5134 1451 56 Calculated with POD code /2/. 5134 1451 57 5134 1451 58 MT= 22 (n,na) cross section 5134 1451 59 Calculated with POD code /2/. 5134 1451 60 5134 1451 61 MT= 28 (n,np) cross section 5134 1451 62 Calculated with POD code /2/. 5134 1451 63 5134 1451 64 MT= 32 (n,nd) cross section 5134 1451 65 Calculated with POD code /2/. 5134 1451 66 5134 1451 67 MT=102 Capture cross section 5134 1451 68 Calculated with POD code /2/. Below 10 eV, an 1/v shape 5134 1451 69 was assumed with 17.4 barns /3/ at 0.0253 eV. 5134 1451 70 5134 1451 71 MT=103 (n,p) cross section 5134 1451 72 Calculated with POD code /2/. 5134 1451 73 5134 1451 74 MT=104 (n,d) cross section 5134 1451 75 Calculated with POD code /2/. 5134 1451 76 5134 1451 77 MT=105 (n,t) cross section 5134 1451 78 Calculated with POD code /2/. 5134 1451 79 5134 1451 80 MT=106 (n,He3) cross section 5134 1451 81 Calculated with POD code /2/. 5134 1451 82 5134 1451 83 MT=107 (n,a) cross section 5134 1451 84 Calculated with POD code /2/. 5134 1451 85 5134 1451 86 MT=203 (n,xp) cross section 5134 1451 87 Calculated with POD code /2/. 5134 1451 88 5134 1451 89 MT=204 (n,xd) cross section 5134 1451 90 Calculated with POD code /2/. 5134 1451 91 5134 1451 92 MT=205 (n,xt) cross section 5134 1451 93 Calculated with POD code /2/. 5134 1451 94 5134 1451 95 MT=206 (n,xHe3) cross section 5134 1451 96 Calculated with POD code /2/. 5134 1451 97 5134 1451 98 MT=207 (n,xa) cross section 5134 1451 99 Calculated with POD code /2/. 5134 1451 100 5134 1451 101 MF= 4 Angular distributions of emitted neutrons 5134 1451 102 MT= 2 Elastic scattering 5134 1451 103 Calculated with POD code /2/. 5134 1451 104 5134 1451 105 MF= 6 Energy-angle distributions of emitted particles 5134 1451 106 MT= 16 (n,2n) reaction 5134 1451 107 Neutron spectra calculated with POD/2/. 5134 1451 108 5134 1451 109 MT= 17 (n,3n) reaction 5134 1451 110 Neutron spectra calculated with POD/2/. 5134 1451 111 5134 1451 112 MT= 22 (n,na) reaction 5134 1451 113 Neutron spectra calculated with POD/2/. 5134 1451 114 5134 1451 115 MT= 28 (n,np) reaction 5134 1451 116 Neutron spectra calculated with POD/2/. 5134 1451 117 5134 1451 118 MT= 32 (n,nd) reaction 5134 1451 119 Neutron spectra calculated with POD/2/. 5134 1451 120 5134 1451 121 MT= 51 (n,n') reaction 5134 1451 122 Neutron angular distributions calculated with POD/2/. 5134 1451 123 5134 1451 124 MT= 52 (n,n') reaction 5134 1451 125 Neutron angular distributions calculated with POD/2/. 5134 1451 126 5134 1451 127 MT= 53 (n,n') reaction 5134 1451 128 Neutron angular distributions calculated with POD/2/. 5134 1451 129 5134 1451 130 MT= 54 (n,n') reaction 5134 1451 131 Neutron angular distributions calculated with POD/2/. 5134 1451 132 5134 1451 133 MT= 55 (n,n') reaction 5134 1451 134 Neutron angular distributions calculated with POD/2/. 5134 1451 135 5134 1451 136 MT= 56 (n,n') reaction 5134 1451 137 Neutron angular distributions calculated with POD/2/. 5134 1451 138 5134 1451 139 MT= 57 (n,n') reaction 5134 1451 140 Neutron angular distributions calculated with POD/2/. 5134 1451 141 5134 1451 142 MT= 58 (n,n') reaction 5134 1451 143 Neutron angular distributions calculated with POD/2/. 5134 1451 144 5134 1451 145 MT= 59 (n,n') reaction 5134 1451 146 Neutron angular distributions calculated with POD/2/. 5134 1451 147 5134 1451 148 MT= 60 (n,n') reaction 5134 1451 149 Neutron angular distributions calculated with POD/2/. 5134 1451 150 5134 1451 151 MT= 61 (n,n') reaction 5134 1451 152 Neutron angular distributions calculated with POD/2/. 5134 1451 153 5134 1451 154 MT= 62 (n,n') reaction 5134 1451 155 Neutron angular distributions calculated with POD/2/. 5134 1451 156 5134 1451 157 MT= 63 (n,n') reaction 5134 1451 158 Neutron angular distributions calculated with POD/2/. 5134 1451 159 5134 1451 160 MT= 64 (n,n') reaction 5134 1451 161 Neutron angular distributions calculated with POD/2/. 5134 1451 162 5134 1451 163 MT= 65 (n,n') reaction 5134 1451 164 Neutron angular distributions calculated with POD/2/. 5134 1451 165 5134 1451 166 MT= 66 (n,n') reaction 5134 1451 167 Neutron angular distributions calculated with POD/2/. 5134 1451 168 5134 1451 169 MT= 67 (n,n') reaction 5134 1451 170 Neutron angular distributions calculated with POD/2/. 5134 1451 171 5134 1451 172 MT= 68 (n,n') reaction 5134 1451 173 Neutron angular distributions calculated with POD/2/. 5134 1451 174 5134 1451 175 MT= 69 (n,n') reaction 5134 1451 176 Neutron angular distributions calculated with POD/2/. 5134 1451 177 5134 1451 178 MT= 70 (n,n') reaction 5134 1451 179 Neutron angular distributions calculated with POD/2/. 5134 1451 180 5134 1451 181 MT= 71 (n,n') reaction 5134 1451 182 Neutron angular distributions calculated with POD/2/. 5134 1451 183 5134 1451 184 MT= 72 (n,n') reaction 5134 1451 185 Neutron angular distributions calculated with POD/2/. 5134 1451 186 5134 1451 187 MT= 73 (n,n') reaction 5134 1451 188 Neutron angular distributions calculated with POD/2/. 5134 1451 189 5134 1451 190 MT= 74 (n,n') reaction 5134 1451 191 Neutron angular distributions calculated with POD/2/. 5134 1451 192 5134 1451 193 MT= 75 (n,n') reaction 5134 1451 194 Neutron angular distributions calculated with POD/2/. 5134 1451 195 5134 1451 196 MT= 76 (n,n') reaction 5134 1451 197 Neutron angular distributions calculated with POD/2/. 5134 1451 198 5134 1451 199 MT= 77 (n,n') reaction 5134 1451 200 Neutron angular distributions calculated with POD/2/. 5134 1451 201 5134 1451 202 MT= 78 (n,n') reaction 5134 1451 203 Neutron angular distributions calculated with POD/2/. 5134 1451 204 5134 1451 205 MT= 79 (n,n') reaction 5134 1451 206 Neutron angular distributions calculated with POD/2/. 5134 1451 207 5134 1451 208 MT= 80 (n,n') reaction 5134 1451 209 Neutron angular distributions calculated with POD/2/. 5134 1451 210 5134 1451 211 MT= 81 (n,n') reaction 5134 1451 212 Neutron angular distributions calculated with POD/2/. 5134 1451 213 5134 1451 214 MT= 82 (n,n') reaction 5134 1451 215 Neutron angular distributions calculated with POD/2/. 5134 1451 216 5134 1451 217 MT= 83 (n,n') reaction 5134 1451 218 Neutron angular distributions calculated with POD/2/. 5134 1451 219 5134 1451 220 MT= 84 (n,n') reaction 5134 1451 221 Neutron angular distributions calculated with POD/2/. 5134 1451 222 5134 1451 223 MT= 91 (n,n') reaction 5134 1451 224 Neutron spectra calculated with POD/2/. 5134 1451 225 5134 1451 226 MT= 203 (n,xp) reaction 5134 1451 227 Proton spectra calculated with POD/2/. 5134 1451 228 5134 1451 229 MT= 204 (n,xd) reaction 5134 1451 230 Deuteron spectra calculated with POD/2/. 5134 1451 231 5134 1451 232 MT= 205 (n,xt) reaction 5134 1451 233 Triton spectra calculated with POD/2/. 5134 1451 234 5134 1451 235 MT= 206 (n,xHe3) reaction 5134 1451 236 He3 spectra calculated with POD/2/. 5134 1451 237 5134 1451 238 MT= 207 (n,xa) reaction 5134 1451 239 Alpha spectra calculated with POD/2/. 5134 1451 240 5134 1451 241 MF= 8 Information on decay data 5134 1451 242 MT= 4 (n,n') reaction 5134 1451 243 5134 1451 244 MT= 16 (n,2n) reaction 5134 1451 245 5134 1451 246 MT= 17 (n,3n) reaction 5134 1451 247 5134 1451 248 MT= 22 (n,na) reaction 5134 1451 249 5134 1451 250 MT= 28 (n,np) reaction 5134 1451 251 5134 1451 252 MT= 32 (n,nd) reaction 5134 1451 253 5134 1451 254 MT=102 (n,g) reaction 5134 1451 255 5134 1451 256 MT=103 (n,p) reaction 5134 1451 257 5134 1451 258 MT=104 (n,d) reaction 5134 1451 259 5134 1451 260 MT=105 (n,t) reaction 5134 1451 261 5134 1451 262 MT=106 (n,He3) reaction 5134 1451 263 5134 1451 264 MT=107 (n,a) reaction 5134 1451 265 5134 1451 266 MF=10 Nuclide production cross sections 5134 1451 267 MT= 4 Partial (n,n') reactions 5134 1451 268 Calculated with POD code /2/. 5134 1451 269 5134 1451 270 MT= 17 Partial (n,3n) reactions 5134 1451 271 Calculated with POD code /2/. 5134 1451 272 5134 1451 273 MT= 22 Partial (n,na) reactions 5134 1451 274 Calculated with POD code /2/. 5134 1451 275 5134 1451 276 MT= 28 Partial (n,np) reactions 5134 1451 277 Calculated with POD code /2/. 5134 1451 278 5134 1451 279 MT=104 Partial (n,d) reactions 5134 1451 280 Calculated with POD code /2/. 5134 1451 281 5134 1451 282 MT=106 Partial (n,He3) reactions 5134 1451 283 Calculated with POD code /2/. 5134 1451 284 5134 1451 285 MT=107 Partial (n,a) reactions 5134 1451 286 Calculated with POD code /2/. 5134 1451 287 5134 1451 288 MF=12 Gamma-ray multiplicities 5134 1451 289 MT= 3 Non-elastic gamma emission 5134 1451 290 Calculated with POD code /2/. 5134 1451 291 5134 1451 292 MF=14 Gamma-ray angular distributions 5134 1451 293 MT= 3 Non-elastic gamma emission 5134 1451 294 Assumed to be isotropic. 5134 1451 295 5134 1451 296 MF=15 Gamma-ray spectra 5134 1451 297 MT= 3 Non-elastic gamma emission 5134 1451 298 Calculated with POD code /2/. 5134 1451 299 5134 1451 300 5134 1451 301 5134 1451 302 *************************************************************** 5134 1451 303 * Nuclear Model Calculations with POD Code /2/ * 5134 1451 304 *************************************************************** 5134 1451 305 1. Theoretical models 5134 1451 306 The POD code is based on the spherical optical model, the 5134 1451 307 distorted-wave Born approximaiton (DWBA), one-component exciton 5134 1451 308 preequilibrium model, and the Hauser-Feshbach-Moldauer statis- 5134 1451 309 tical model. With the preequilibrim model, semi-empirical 5134 1451 310 pickup and knockout process can be taken into account for 5134 1451 311 composite-particle emission. The gamma-ray emission from the 5134 1451 312 compound nucleus can be calculated within the framework of the 5134 1451 313 exciton model. The code is capable of reading in particle 5134 1451 314 transmission coefficients calculated by separate spherical or 5134 1451 315 coupled-channel optical model code. 5134 1451 316 5134 1451 317 2. Optical model parameters 5134 1451 318 Neutrons: 5134 1451 319 Coupled-channel optical model parameters /4/ 5134 1451 320 Protons: 5134 1451 321 Koning and Delaroche /5/ 5134 1451 322 Deuterons: 5134 1451 323 Lohr and Haeberli /6/ 5134 1451 324 Tritons: 5134 1451 325 Becchetti and Greenlees /7/ 5134 1451 326 He-3: 5134 1451 327 Becchetti and Greenlees /7/ 5134 1451 328 Alphas: 5134 1451 329 Lemos /8/ potentials modified by Arthur and Young /9/ 5134 1451 330 5134 1451 331 3. Level scheme of Sb-124 5134 1451 332 ------------------------- 5134 1451 333 No. Ex(MeV) J PI 5134 1451 334 ------------------------- 5134 1451 335 0 0.00000 3 - 5134 1451 336 1 0.01086 5 + 5134 1451 337 2 0.03684 8 - 5134 1451 338 3 0.04080 3 + 5134 1451 339 4 0.08076 4 + 5134 1451 340 5 0.08760 4 - 5134 1451 341 6 0.10365 4 - 5134 1451 342 7 0.12523 6 - 5134 1451 343 8 0.13169 5 - 5134 1451 344 9 0.15000 1 + 5134 1451 345 10 0.18005 7 - 5134 1451 346 11 0.19598 5 + 5134 1451 347 12 0.21460 3 + 5134 1451 348 13 0.22150 2 - 5134 1451 349 14 0.23150 5 + 5134 1451 350 15 0.24837 1 + 5134 1451 351 16 0.28713 4 + 5134 1451 352 17 0.36833 9 + 5134 1451 353 18 0.37182 8 - 5134 1451 354 19 0.38453 5 - 5134 1451 355 20 0.38629 3 + 5134 1451 356 21 0.40288 4 + 5134 1451 357 22 0.41906 4 - 5134 1451 358 23 0.43917 4 - 5134 1451 359 24 0.44567 6 - 5134 1451 360 25 0.47126 3 + 5134 1451 361 26 0.48400 4 + 5134 1451 362 27 0.52269 2 + 5134 1451 363 28 0.56510 1 - 5134 1451 364 29 0.58192 3 - 5134 1451 365 30 0.59300 5 - 5134 1451 366 31 0.59866 3 - 5134 1451 367 32 0.61269 5 - 5134 1451 368 33 0.64206 6 + 5134 1451 369 34 0.64265 5 - 5134 1451 370 ------------------------- 5134 1451 371 Levels above 0.65265 MeV are assumed to be continuous. 5134 1451 372 A giant resonance, which was estimated from DWBA, was added to 5134 1451 373 the continumm at Ex = 2.3 MeV. 5134 1451 374 5134 1451 375 4. Level density parameters 5134 1451 376 Energy-dependent parameters of Mengoni-Nakajima /10/ were used 5134 1451 377 ---------------------------------------------------------- 5134 1451 378 Nuclei a* Pair Esh T E0 Ematch Elv_max 5134 1451 379 1/MeV MeV MeV MeV MeV MeV MeV 5134 1451 380 ---------------------------------------------------------- 5134 1451 381 Sb-125 14.870 1.073 -0.068 0.553 0.610 4.053 2.299 5134 1451 382 Sb-124 14.872 0.000 0.763 0.688 -1.937 5.528 0.643 5134 1451 383 Sb-123 14.667 1.082 1.092 0.594 0.036 5.016 1.773 5134 1451 384 Sb-122 14.721 0.000 1.681 0.610 -1.394 4.451 0.605 5134 1451 385 Sn-124 15.404 2.155 -0.998 0.704 0.534 7.380 2.879 5134 1451 386 Sn-123 15.969 1.082 -0.017 0.714 -1.324 7.311 1.301 5134 1451 387 Sn-122 15.193 2.173 0.164 0.629 0.927 6.532 3.036 5134 1451 388 In-122 15.117 0.000 0.977 0.559 -0.857 3.517 0.229 5134 1451 389 In-121 14.463 1.091 1.390 0.614 -0.170 5.389 1.504 5134 1451 390 In-120 14.908 0.000 1.930 0.635 -1.806 5.074 0.070 5134 1451 391 ---------------------------------------------------------- 5134 1451 392 5134 1451 393 5. Gamma-ray strength functions 5134 1451 394 M1, E2: Standard Lorentzian (SLO) 5134 1451 395 E1 : Modified Lorentzian (MLO) /11/ 5134 1451 396 5134 1451 397 6. Preequilibrium process 5134 1451 398 Preequilibrium is on for n, p, d, t, He-3, and alpha. 5134 1451 399 Preequilibrium capture is on. 5134 1451 400 5134 1451 401 References 5134 1451 402 1) K.Shibata, J. Nucl. Sci. Technol. 51, 425 (2014). 5134 1451 403 2) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 5134 1451 404 3) K.Nishimura et al., J. Nucl. Sci. Technol., 16, 546 (1979). 5134 1451 405 4) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 5134 1451 406 5) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 5134 1451 407 6) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 5134 1451 408 7) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization 5134 1451 409 Phenomena in Nuclear Reactions," p.682, The University 5134 1451 410 of Wisconsin Press (1971). 5134 1451 411 8) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 5134 1451 412 9) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 5134 1451 413 10) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 5134 1451 414 (1994). 5134 1451 415 11) V.A.Plujko et al., J. Nucl. Sci. Technol. Suppl. 2, 811 5134 1451 416 (2002). 5134 1451 417 5134 1451 418 1 451 445 15134 1451 419 2 151 4 15134 1451 420 3 4 31 15134 1451 421 3 16 10 15134 1451 422 3 32 7 15134 1451 423 3 102 114 15134 1451 424 3 103 14 15134 1451 425 3 105 9 15134 1451 426 8 4 2 15134 1451 427 8 16 2 15134 1451 428 8 17 3 15134 1451 429 8 22 4 15134 1451 430 8 28 3 15134 1451 431 8 32 2 15134 1451 432 8 102 2 15134 1451 433 8 103 2 15134 1451 434 8 104 3 15134 1451 435 8 105 2 15134 1451 436 8 106 3 15134 1451 437 8 107 3 15134 1451 438 10 4 38 15134 1451 439 10 17 9 15134 1451 440 10 22 19 15134 1451 441 10 28 15 15134 1451 442 10 104 17 15134 1451 443 10 106 9 15134 1451 444 10 107 23 15134 1451 445 5134 1 099999 5134 0 0 0 5.112400+4 1.228415+2 0 0 1 05134 2151 1 5.112400+4 1.000000+0 0 0 1 05134 2151 2 1.000000+1 1.000000+5 0 0 0 05134 2151 3 3.000000+0 5.381700-1 0 0 0 05134 2151 4 5134 2 099999 5134 0 0 0 5.112400+4 1.228415+2 0 0 0 05134 3 4 1 0.000000+0-1.086300+4 0 0 1 835134 3 4 2 83 2 5134 3 4 3 1.095143+4 0.000000+0 2.000000+4 4.713000-2 3.000000+4 6.941000-25134 3 4 4 3.714393+4 8.019019-2 4.000000+4 8.450000-2 4.113617+4 8.561231-25134 3 4 5 5.000000+4 2.413900-1 6.000000+4 3.031004-1 7.000000+4 3.456035-15134 3 4 6 8.000000+4 3.756085-1 8.142146+4 3.748702-1 8.831513+4 4.345242-15134 3 4 7 9.000000+4 4.855941-1 1.000000+5 5.399609-1 1.044948+5 5.434062-15134 3 4 8 1.262484+5 5.888030-1 1.327651+5 6.031988-1 1.512211+5 6.524185-15134 3 4 9 1.815167+5 7.513981-1 1.975774+5 8.039003-1 2.000000+5 8.189808-15134 3 4 10 2.163500+5 8.110957-1 2.233031+5 8.152001-1 2.333845+5 8.290562-15134 3 4 11 2.503909+5 8.574671-1 2.894664+5 9.351761-1 3.000000+5 9.734841-15134 3 4 12 3.713314+5 9.984345-1 3.748499+5 9.996653-1 3.876643+5 1.004156+05134 3 4 13 3.894326+5 1.005157+0 4.000000+5 1.027108+0 4.061577+5 1.024287+05134 3 4 14 4.224734+5 1.022295+0 4.427471+5 1.026540+0 4.493000+5 1.030142+05134 3 4 15 4.750963+5 1.045738+0 4.879390+5 1.062465+0 5.000000+5 1.086209+05134 3 4 16 5.269460+5 1.090227+0 5.697002+5 1.108423+0 5.866531+5 1.117568+05134 3 4 17 5.978274+5 1.129166+0 6.000000+5 1.132330+0 6.035314+5 1.134798+05134 3 4 18 6.176807+5 1.148274+0 6.472837+5 1.179325+0 6.478836+5 1.179972+05134 3 4 19 6.579650+5 1.191857+0 7.000000+5 1.241497+0 8.000000+5 1.263038+05134 3 4 20 9.000000+5 1.295268+0 1.000000+6 1.318495+0 1.250000+6 1.387622+05134 3 4 21 1.500000+6 1.456109+0 2.000000+6 1.542259+0 2.500000+6 1.615490+05134 3 4 22 3.000000+6 1.718554+0 3.500000+6 1.872748+0 4.000000+6 2.029174+05134 3 4 23 4.500000+6 2.118487+0 5.000000+6 2.139946+0 5.500000+6 2.112039+05134 3 4 24 6.000000+6 2.061719+0 6.500000+6 2.011386+0 7.000000+6 1.847017+05134 3 4 25 7.500000+6 1.605345+0 8.000000+6 1.337826+0 8.500000+6 1.160251+05134 3 4 26 9.000000+6 9.945054-1 9.500000+6 8.829085-1 1.000000+7 7.639032-15134 3 4 27 1.100000+7 5.876371-1 1.200000+7 4.659792-1 1.300000+7 3.872917-15134 3 4 28 1.400000+7 3.362254-1 1.450000+7 3.195957-1 1.500000+7 3.032482-15134 3 4 29 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