JENDL-5 (Neutron sublibrary (activation cs)) Mo- 99 0 0 0 0 4.209900+4 9.805805+1 0 0 6 14246 1451 1 0.000000+0 1.000000+0 0 0 0 64246 1451 2 1.000000+0 2.000000+7 0 0 10 54246 1451 3 2.936000+2 0.000000+0 4 0 398 264246 1451 4 42-Mo- 99 JAEA EVAL-MAR09 K.Shibata, A.Ichihara, S.Kunieda 4246 1451 5 DIST-DEC21 20091112 4246 1451 6 ----JENDL-5 MATERIAL 4246 4246 1451 7 -----INCIDENT NEUTRON DATA 4246 1451 8 ------ENDF-6 FORMAT 4246 1451 9 4246 1451 10 History 4246 1451 11 09-03 The data above the resolved resonance region were evaluated 4246 1451 12 by K.Shibata, A.Ichihara, and S.Kunieda /1/. 4246 1451 13 09-10 Compiled by K.Shibata 4246 1451 14 21-11 revised by O.Iwamoto 4246 1451 15 (MF8/MT16,17,22,28,32,102-107) JENDL/AD-2017 adopted 4246 1451 16 (MF8/MT4) added 4246 1451 17 (MF10/MT16,28,32,103-105,107) JENDL/AD-2017 based 4246 1451 18 21-11 above 20 MeV, JENDL/ImPACT-2018 merged by O.Iwamoto 4246 1451 19 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 4246 1451 20 4246 1451 21 4246 1451 22 MF= 1 General information 4246 1451 23 MT=451 Descriptive data and directory 4246 1451 24 4246 1451 25 MF= 2 Resonance parameters 4246 1451 26 MT=151 Resolved and unresolved resoannce parameters 4246 1451 27 No resolved resonance is given. 4246 1451 28 4246 1451 29 Unresolved resonance region: 24 eV - 300 KeV 4246 1451 30 The parameters were obtained by fitting to the total and 4246 1451 31 capture cross sections calculated from POD /2/. The 4246 1451 32 unresolved parameters should be used only for self-shielding4246 1451 33 calculation. 4246 1451 34 4246 1451 35 Thermal cross sections and resonance integrals at 300 K 4246 1451 36 ---------------------------------------------------------- 4246 1451 37 0.0253 eV res. integ. (*) 4246 1451 38 (barns) (barns) 4246 1451 39 ---------------------------------------------------------- 4246 1451 40 Total 1.3760E+01 4246 1451 41 Elastic 5.7329E+00 4246 1451 42 n,gamma 8.0036E+00 3.6868E+01 4246 1451 43 ---------------------------------------------------------- 4246 1451 44 (*) Integrated from 0.5 eV to 10 MeV. 4246 1451 45 4246 1451 46 MF= 3 Neutron cross sections 4246 1451 47 Below 24 eV, the capture and elastic scattering cross sections 4246 1451 48 were taken from JENDL-3.3. 4246 1451 49 4246 1451 50 MT= 1 Total cross section 4246 1451 51 Calculated with POD code /2/. 4246 1451 52 4246 1451 53 MT= 2 Elastic scattering cross section 4246 1451 54 Obtained by subtracting non-elastic cross section from total 4246 1451 55 cross sections. 4246 1451 56 4246 1451 57 MT= 3 Non-elastic cross section 4246 1451 58 Sum of partial non-elastic cross sections. 4246 1451 59 4246 1451 60 MT= 4,51-91 (n,n') cross section 4246 1451 61 Calculated with POD code /2/. 4246 1451 62 4246 1451 63 MT= 16 (n,2n) cross section 4246 1451 64 Calculated with POD code /2/. 4246 1451 65 4246 1451 66 MT= 17 (n,3n) cross section 4246 1451 67 Calculated with POD code /2/. 4246 1451 68 4246 1451 69 MT= 22 (n,na) cross section 4246 1451 70 Calculated with POD code /2/. 4246 1451 71 4246 1451 72 MT= 28 (n,np) cross section 4246 1451 73 Calculated with POD code /2/. 4246 1451 74 4246 1451 75 MT= 32 (n,nd) cross section 4246 1451 76 Calculated with POD code /2/. 4246 1451 77 4246 1451 78 MT=102 Capture cross section 4246 1451 79 Calculated with POD code /2/. 4246 1451 80 4246 1451 81 MT=103 (n,p) cross section 4246 1451 82 Calculated with POD code /2/. 4246 1451 83 4246 1451 84 MT=104 (n,d) cross section 4246 1451 85 Calculated with POD code /2/. 4246 1451 86 4246 1451 87 MT=105 (n,t) cross section 4246 1451 88 Calculated with POD code /2/. 4246 1451 89 4246 1451 90 MT=106 (n,He3) cross section 4246 1451 91 Calculated with POD code /2/. 4246 1451 92 4246 1451 93 MT=107 (n,a) cross section 4246 1451 94 Calculated with POD code /2/. 4246 1451 95 4246 1451 96 MT=203 (n,xp) cross section 4246 1451 97 Calculated with POD code /2/. 4246 1451 98 4246 1451 99 MT=204 (n,xd) cross section 4246 1451 100 Calculated with POD code /2/. 4246 1451 101 4246 1451 102 MT=205 (n,xt) cross section 4246 1451 103 Calculated with POD code /2/. 4246 1451 104 4246 1451 105 MT=206 (n,xHe3) cross section 4246 1451 106 Calculated with POD code /2/. 4246 1451 107 4246 1451 108 MT=207 (n,xa) cross section 4246 1451 109 Calculated with POD code /2/. 4246 1451 110 4246 1451 111 MF= 4 Angular distributions of emitted neutrons 4246 1451 112 MT= 2 Elastic scattering 4246 1451 113 Calculated with POD code /2/. 4246 1451 114 4246 1451 115 MF= 6 Energy-angle distributions of emitted particles 4246 1451 116 MT= 16 (n,2n) reaction 4246 1451 117 Neutron spectra calculated with POD/2/. 4246 1451 118 4246 1451 119 MT= 17 (n,3n) reaction 4246 1451 120 Neutron spectra calculated with POD/2/. 4246 1451 121 4246 1451 122 MT= 22 (n,na) reaction 4246 1451 123 Neutron spectra calculated with POD/2/. 4246 1451 124 4246 1451 125 MT= 28 (n,np) reaction 4246 1451 126 Neutron spectra calculated with POD/2/. 4246 1451 127 4246 1451 128 MT= 32 (n,nd) reaction 4246 1451 129 Neutron spectra calculated with POD/2/. 4246 1451 130 4246 1451 131 MT= 51 (n,n') reaction 4246 1451 132 Neutron angular distributions calculated with POD/2/. 4246 1451 133 4246 1451 134 MT= 52 (n,n') reaction 4246 1451 135 Neutron angular distributions calculated with POD/2/. 4246 1451 136 4246 1451 137 MT= 53 (n,n') reaction 4246 1451 138 Neutron angular distributions calculated with POD/2/. 4246 1451 139 4246 1451 140 MT= 54 (n,n') reaction 4246 1451 141 Neutron angular distributions calculated with POD/2/. 4246 1451 142 4246 1451 143 MT= 55 (n,n') reaction 4246 1451 144 Neutron angular distributions calculated with POD/2/. 4246 1451 145 4246 1451 146 MT= 56 (n,n') reaction 4246 1451 147 Neutron angular distributions calculated with POD/2/. 4246 1451 148 4246 1451 149 MT= 57 (n,n') reaction 4246 1451 150 Neutron angular distributions calculated with POD/2/. 4246 1451 151 4246 1451 152 MT= 58 (n,n') reaction 4246 1451 153 Neutron angular distributions calculated with POD/2/. 4246 1451 154 4246 1451 155 MT= 59 (n,n') reaction 4246 1451 156 Neutron angular distributions calculated with POD/2/. 4246 1451 157 4246 1451 158 MT= 60 (n,n') reaction 4246 1451 159 Neutron angular distributions calculated with POD/2/. 4246 1451 160 4246 1451 161 MT= 61 (n,n') reaction 4246 1451 162 Neutron angular distributions calculated with POD/2/. 4246 1451 163 4246 1451 164 MT= 62 (n,n') reaction 4246 1451 165 Neutron angular distributions calculated with POD/2/. 4246 1451 166 4246 1451 167 MT= 63 (n,n') reaction 4246 1451 168 Neutron angular distributions calculated with POD/2/. 4246 1451 169 4246 1451 170 MT= 64 (n,n') reaction 4246 1451 171 Neutron angular distributions calculated with POD/2/. 4246 1451 172 4246 1451 173 MT= 65 (n,n') reaction 4246 1451 174 Neutron angular distributions calculated with POD/2/. 4246 1451 175 4246 1451 176 MT= 66 (n,n') reaction 4246 1451 177 Neutron angular distributions calculated with POD/2/. 4246 1451 178 4246 1451 179 MT= 67 (n,n') reaction 4246 1451 180 Neutron angular distributions calculated with POD/2/. 4246 1451 181 4246 1451 182 MT= 68 (n,n') reaction 4246 1451 183 Neutron angular distributions calculated with POD/2/. 4246 1451 184 4246 1451 185 MT= 69 (n,n') reaction 4246 1451 186 Neutron angular distributions calculated with POD/2/. 4246 1451 187 4246 1451 188 MT= 70 (n,n') reaction 4246 1451 189 Neutron angular distributions calculated with POD/2/. 4246 1451 190 4246 1451 191 MT= 71 (n,n') reaction 4246 1451 192 Neutron angular distributions calculated with POD/2/. 4246 1451 193 4246 1451 194 MT= 72 (n,n') reaction 4246 1451 195 Neutron angular distributions calculated with POD/2/. 4246 1451 196 4246 1451 197 MT= 73 (n,n') reaction 4246 1451 198 Neutron angular distributions calculated with POD/2/. 4246 1451 199 4246 1451 200 MT= 74 (n,n') reaction 4246 1451 201 Neutron angular distributions calculated with POD/2/. 4246 1451 202 4246 1451 203 MT= 75 (n,n') reaction 4246 1451 204 Neutron angular distributions calculated with POD/2/. 4246 1451 205 4246 1451 206 MT= 76 (n,n') reaction 4246 1451 207 Neutron angular distributions calculated with POD/2/. 4246 1451 208 4246 1451 209 MT= 77 (n,n') reaction 4246 1451 210 Neutron angular distributions calculated with POD/2/. 4246 1451 211 4246 1451 212 MT= 78 (n,n') reaction 4246 1451 213 Neutron angular distributions calculated with POD/2/. 4246 1451 214 4246 1451 215 MT= 79 (n,n') reaction 4246 1451 216 Neutron angular distributions calculated with POD/2/. 4246 1451 217 4246 1451 218 MT= 80 (n,n') reaction 4246 1451 219 Neutron angular distributions calculated with POD/2/. 4246 1451 220 4246 1451 221 MT= 81 (n,n') reaction 4246 1451 222 Neutron angular distributions calculated with POD/2/. 4246 1451 223 4246 1451 224 MT= 82 (n,n') reaction 4246 1451 225 Neutron angular distributions calculated with POD/2/. 4246 1451 226 4246 1451 227 MT= 83 (n,n') reaction 4246 1451 228 Neutron angular distributions calculated with POD/2/. 4246 1451 229 4246 1451 230 MT= 84 (n,n') reaction 4246 1451 231 Neutron angular distributions calculated with POD/2/. 4246 1451 232 4246 1451 233 MT= 85 (n,n') reaction 4246 1451 234 Neutron angular distributions calculated with POD/2/. 4246 1451 235 4246 1451 236 MT= 86 (n,n') reaction 4246 1451 237 Neutron angular distributions calculated with POD/2/. 4246 1451 238 4246 1451 239 MT= 87 (n,n') reaction 4246 1451 240 Neutron angular distributions calculated with POD/2/. 4246 1451 241 4246 1451 242 MT= 88 (n,n') reaction 4246 1451 243 Neutron angular distributions calculated with POD/2/. 4246 1451 244 4246 1451 245 MT= 89 (n,n') reaction 4246 1451 246 Neutron angular distributions calculated with POD/2/. 4246 1451 247 4246 1451 248 MT= 90 (n,n') reaction 4246 1451 249 Neutron angular distributions calculated with POD/2/. 4246 1451 250 4246 1451 251 MT= 91 (n,n') reaction 4246 1451 252 Neutron spectra calculated with POD/2/. 4246 1451 253 4246 1451 254 MT= 203 (n,xp) reaction 4246 1451 255 Proton spectra calculated with POD/2/. 4246 1451 256 4246 1451 257 MT= 204 (n,xd) reaction 4246 1451 258 Deuteron spectra calculated with POD/2/. 4246 1451 259 4246 1451 260 MT= 205 (n,xt) reaction 4246 1451 261 Triton spectra calculated with POD/2/. 4246 1451 262 4246 1451 263 MT= 206 (n,xHe3) reaction 4246 1451 264 He3 spectra calculated with POD/2/. 4246 1451 265 4246 1451 266 MT= 207 (n,xa) reaction 4246 1451 267 Alpha spectra calculated with POD/2/. 4246 1451 268 4246 1451 269 MF=12 Gamma-ray multiplicities 4246 1451 270 MT= 3 Non-elastic gamma emission 4246 1451 271 Calculated with POD code /2/. 4246 1451 272 4246 1451 273 MF=14 Gamma-ray angular distributions 4246 1451 274 MT= 3 Non-elastic gamma emission 4246 1451 275 Assumed to be isotropic. 4246 1451 276 4246 1451 277 MF=15 Gamma-ray spectra 4246 1451 278 MT= 3 Non-elastic gamma emission 4246 1451 279 Calculated with POD code /2/. 4246 1451 280 4246 1451 281 4246 1451 282 4246 1451 283 *************************************************************** 4246 1451 284 * Nuclear Model Calculations with POD Code /2/ * 4246 1451 285 *************************************************************** 4246 1451 286 1. Theoretical models 4246 1451 287 The POD code is based on the spherical optical model, the 4246 1451 288 distorted-wave Born approximaiton (DWBA), one-component exciton 4246 1451 289 preequilibrium model, and the Hauser-Feshbach-Moldauer statis- 4246 1451 290 tical model. With the preequilibrim model, semi-empirical 4246 1451 291 pickup and knockout process can be taken into account for 4246 1451 292 composite-particle emission. The gamma-ray emission from the 4246 1451 293 compound nucleus can be calculated within the framework of the 4246 1451 294 exciton model. The code is capable of reading in particle 4246 1451 295 transmission coefficients calculated by separate spherical or 4246 1451 296 coupled-channel optical model code. 4246 1451 297 4246 1451 298 2. Optical model parameters 4246 1451 299 Neutrons: 4246 1451 300 Coupled-channel optical model parameters /3/ 4246 1451 301 Protons: 4246 1451 302 Koning and Delaroche /4/ 4246 1451 303 Deuterons: 4246 1451 304 Lohr and Haeberli /5/ 4246 1451 305 Tritons: 4246 1451 306 Becchetti and Greenlees /6/ 4246 1451 307 He-3: 4246 1451 308 Becchetti and Greenlees /6/ 4246 1451 309 Alphas: 4246 1451 310 Lemos /7/ potentials modified by Arthur and Young /8/ 4246 1451 311 4246 1451 312 3. Level scheme of Mo- 99 4246 1451 313 ------------------------- 4246 1451 314 No. Ex(MeV) J PI 4246 1451 315 ------------------------- 4246 1451 316 0 0.00000 1/2 + 4246 1451 317 1 0.09778 5/2 + 4246 1451 318 2 0.23551 7/2 + 4246 1451 319 3 0.35124 3/2 + 4246 1451 320 4 0.52520 1/2 + 4246 1451 321 5 0.54868 3/2 + 4246 1451 322 6 0.61508 5/2 + 4246 1451 323 7 0.63177 3/2 + 4246 1451 324 8 0.68450 11/2 - 4246 1451 325 9 0.69797 7/2 + 4246 1451 326 10 0.75240 5/2 + 4246 1451 327 11 0.75400 7/2 + 4246 1451 328 12 0.79284 3/2 + 4246 1451 329 13 0.86710 7/2 - 4246 1451 330 14 0.89032 3/2 + 4246 1451 331 15 0.90542 1/2 + 4246 1451 332 16 0.90560 9/2 + 4246 1451 333 17 0.92400 5/2 + 4246 1451 334 18 0.94469 5/2 + 4246 1451 335 19 1.02564 3/2 + 4246 1451 336 20 1.03000 3/2 - 4246 1451 337 21 1.04850 7/2 + 4246 1451 338 22 1.14280 7/2 + 4246 1451 339 23 1.14800 7/2 - 4246 1451 340 24 1.16540 15/2 - 4246 1451 341 25 1.16744 5/2 + 4246 1451 342 26 1.19600 5/2 + 4246 1451 343 27 1.19776 3/2 + 4246 1451 344 28 1.25420 5/2 + 4246 1451 345 29 1.26100 1/2 + 4246 1451 346 30 1.27380 9/2 - 4246 1451 347 31 1.28040 7/2 + 4246 1451 348 32 1.28300 3/2 - 4246 1451 349 33 1.31340 11/2 + 4246 1451 350 34 1.34250 7/2 + 4246 1451 351 35 1.35260 7/2 + 4246 1451 352 36 1.35420 11/2 - 4246 1451 353 37 1.36780 5/2 + 4246 1451 354 38 1.38260 3/2 + 4246 1451 355 39 1.40050 7/2 - 4246 1451 356 40 1.40480 17/2 + 4246 1451 357 ------------------------- 4246 1451 358 Levels above 1.41480 MeV are assumed to be continuous. 4246 1451 359 4246 1451 360 4. Level density parameters 4246 1451 361 Energy-dependent parameters of Mengoni-Nakajima /9/ were used 4246 1451 362 ---------------------------------------------------------- 4246 1451 363 Nuclei a* Pair Esh T E0 Ematch Elv_max 4246 1451 364 1/MeV MeV MeV MeV MeV MeV MeV 4246 1451 365 ---------------------------------------------------------- 4246 1451 366 Mo-100 12.837 2.400 3.838 0.682 0.172 8.104 2.432 4246 1451 367 Mo- 99 13.082 1.206 3.377 0.716 -1.379 7.501 1.405 4246 1451 368 Mo- 98 13.582 2.424 2.452 0.685 0.275 8.035 2.350 4246 1451 369 Mo- 97 12.902 1.218 1.698 0.757 -1.128 7.419 1.120 4246 1451 370 Nb- 99 12.177 1.206 4.589 0.647 -0.587 6.199 1.264 4246 1451 371 Nb- 98 12.575 0.000 3.150 0.552 -0.760 3.224 0.226 4246 1451 372 Nb- 97 11.968 1.218 2.747 0.628 0.171 5.168 2.106 4246 1451 373 Zr- 97 12.179 1.218 2.499 0.394 1.420 2.287 2.265 4246 1451 374 Zr- 96 12.403 2.449 2.151 0.635 1.347 6.496 3.608 4246 1451 375 Zr- 95 11.644 1.231 1.510 0.689 0.170 5.479 2.025 4246 1451 376 ---------------------------------------------------------- 4246 1451 377 4246 1451 378 5. Gamma-ray strength functions 4246 1451 379 M1, E2: Standard Lorentzian (SLO) 4246 1451 380 E1 : Generalized Lorentzian (GLO) /10/ 4246 1451 381 4246 1451 382 6. Preequilibrium process 4246 1451 383 Preequilibrium is on for n, p, d, t, He-3, and alpha. 4246 1451 384 Preequilibrium capture is on. 4246 1451 385 4246 1451 386 References 4246 1451 387 1) K.Shibata, A.Ichihara, S.Kunieda, J. Nucl. Sci. Technol., 4246 1451 388 46, 278 (2009). 4246 1451 389 2) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 4246 1451 390 3) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 4246 1451 391 4) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 4246 1451 392 5) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 4246 1451 393 6) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization 4246 1451 394 Phenomena in Nuclear Reactions," p.682, The University 4246 1451 395 of Wisconsin Press (1971). 4246 1451 396 7) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 4246 1451 397 8) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 4246 1451 398 9) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 4246 1451 399 (1994). 4246 1451 400 10) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990). 4246 1451 401 4246 1451 402 1 451 428 14246 1451 403 2 151 4 14246 1451 404 3 4 30 14246 1451 405 3 16 10 14246 1451 406 3 17 6 14246 1451 407 3 22 8 14246 1451 408 3 102 117 14246 1451 409 3 106 6 14246 1451 410 3 107 14 14246 1451 411 8 4 2 14246 1451 412 8 16 2 04246 1451 413 8 17 2 14246 1451 414 8 22 2 14246 1451 415 8 28 3 14246 1451 416 8 32 3 14246 1451 417 8 102 2 14246 1451 418 8 103 3 14246 1451 419 8 104 3 14246 1451 420 8 105 3 14246 1451 421 8 106 2 14246 1451 422 8 107 2 04246 1451 423 10 28 13 14246 1451 424 10 32 9 14246 1451 425 10 103 21 14246 1451 426 10 104 15 14246 1451 427 10 105 15 14246 1451 428 4246 1 099999 4246 0 0 0 4.209900+4 9.805805+1 0 0 1 04246 2151 1 4.209900+4 1.000000+0 0 0 1 04246 2151 2 2.400000+1 3.000000+5 0 0 0 04246 2151 3 5.000000-1 6.828100-1 0 0 0 04246 2151 4 4246 2 099999 4246 0 0 0 4.209900+4 9.805805+1 0 0 0 04246 3 4 1 0.000000+0-9.778500+4 0 0 1 804246 3 4 2 80 2 4246 3 4 3 9.878222+4 0.000000+0 1.000000+5 4.330000-3 2.000000+5 1.097000+04246 3 4 4 2.379097+5 1.140975+0 3.000000+5 1.330400+0 3.548220+5 1.296849+04246 3 4 5 4.000000+5 1.566000+0 5.000000+5 1.737500+0 5.305530+5 1.687760+04246 3 4 6 5.542755+5 1.710626+0 6.000000+5 1.894600+0 6.213526+5 1.875447+04246 3 4 7 6.382128+5 1.884483+0 6.914806+5 2.021919+0 7.000000+5 2.043951+04246 3 4 8 7.050879+5 2.040464+0 7.600730+5 2.028115+0 7.616893+5 2.029339+04246 3 4 9 8.000000+5 2.075147+0 8.009254+5 2.074186+0 8.759427+5 2.079699+04246 3 4 10 8.993995+5 2.090182+0 9.000000+5 2.093658+0 9.146535+5 2.079416+04246 3 4 11 9.148353+5 2.079361+0 9.334230+5 2.075806+0 9.543240+5 2.084234+04246 3 4 12 1.000000+6 2.128722+0 1.036100+6 2.088159+0 1.040504+6 2.083979+04246 3 4 13 1.059193+6 2.069539+0 1.154454+6 2.005499+0 1.159707+6 2.002572+04246 3 4 14 1.177285+6 1.994278+0 1.179346+6 1.993305+0 1.208197+6 1.985000+04246 3 4 15 1.209975+6 1.984831+0 1.266990+6 1.992357+0 1.273860+6 1.994725+04246 3 4 16 1.286790+6 2.001621+0 1.293458+6 2.005408+0 1.296084+6 2.007278+04246 3 4 17 1.326794+6 2.037275+0 1.356191+6 2.066668+0 1.366394+6 2.078486+04246 3 4 18 1.368010+6 2.080616+0 1.381749+6 2.098783+0 1.396700+6 2.122315+04246 3 4 19 1.414782+6 2.156182+0 1.419126+6 2.164848+0 1.429228+6 2.185001+04246 3 4 20 1.500000+6 2.327161+0 2.000000+6 2.360279+0 2.500000+6 2.287368+04246 3 4 21 3.000000+6 2.158979+0 3.500000+6 2.042093+0 4.000000+6 1.965246+04246 3 4 22 4.500000+6 1.932194+0 5.000000+6 1.929915+0 5.500000+6 1.944252+04246 3 4 23 6.000000+6 1.960807+0 6.500000+6 1.859549+0 7.000000+6 1.643266+04246 3 4 24 7.500000+6 1.368911+0 8.000000+6 1.095329+0 8.500000+6 8.737028-14246 3 4 25 9.000000+6 7.039186-1 9.500000+6 5.870238-1 1.000000+7 5.003609-14246 3 4 26 1.100000+7 3.963820-1 1.200000+7 3.399412-1 1.300000+7 3.053189-14246 3 4 27 1.400000+7 2.832567-1 1.450000+7 2.735315-1 1.500000+7 2.663853-14246 3 4 28 1.600000+7 2.525875-1 1.700000+7 2.404328-1 1.800000+7 2.292992-14246 3 4 29 1.900000+7 2.184941-1 2.000000+7 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