JENDL-5 (Neutron sublibrary (activation cs)) Kr- 85 0 0 0 0 3.608500+4 8.418309+1 0 0 6 13646 1451 1 0.000000+0 1.000000+0 0 0 0 63646 1451 2 1.000000+0 2.000000+7 0 0 10 53646 1451 3 2.936000+2 0.000000+0 4 0 363 263646 1451 4 36-Kr- 85 JAEA EVAL-AUG09 K.Shibata, A.Ichihara, S.Kunieda 3646 1451 5 DIST-DEC21 20091004 3646 1451 6 ----JENDL-5 MATERIAL 3646 3646 1451 7 -----INCIDENT NEUTRON DATA 3646 1451 8 ------ENDF-6 FORMAT 3646 1451 9 3646 1451 10 History 3646 1451 11 09-08 Evaluated by K. Shibata, A. Ichihara and S. Kunieda. 3646 1451 12 09-10 Compiled by K. Shibata. 3646 1451 13 21-11 revised by O.Iwamoto 3646 1451 14 (MF8/MT4,16,17,22,28,32,102-107) added 3646 1451 15 3646 1451 16 MF= 1 General information 3646 1451 17 MT=451 Descriptive data and directory 3646 1451 18 3646 1451 19 MF= 2 Resonance parameters 3646 1451 20 MT=151 Resolved and unresolved resonance parameters 3646 1451 21 No resolved resonance region is given. The scattering and 3646 1451 22 capture cross sections are the same as those contained in 3646 1451 23 JENDL-3.3 below 1 keV. 3646 1451 24 3646 1451 25 Unresolved resonance region: 1 keV - 1 MeV 3646 1451 26 The parameters were obtained by fitting to the total and 3646 1451 27 capture cross sections calculated from POD /1/. The 3646 1451 28 unresolved parameters should be used only for self-shielding3646 1451 29 calculation. 3646 1451 30 3646 1451 31 Thermal cross sections and resonance integrals at 300 K 3646 1451 32 ---------------------------------------------------------- 3646 1451 33 0.0253 eV res. integ. (*) 3646 1451 34 (barns) (barns) 3646 1451 35 ---------------------------------------------------------- 3646 1451 36 Total 7.9765E+00 3646 1451 37 Elastic 6.2945E+00 3646 1451 38 n,gamma 1.6608E+00 3.5104E+00 3646 1451 39 ---------------------------------------------------------- 3646 1451 40 (*) Integrated from 0.5 eV to 10 MeV. 3646 1451 41 3646 1451 42 MF= 3 Neutron cross sections 3646 1451 43 MT= 1 Total cross section 3646 1451 44 Calculated with POD code /1/ above 1 keV. Sum of non-elastic 3646 1451 45 and elastic cross sections below 1 keV. 3646 1451 46 3646 1451 47 MT= 2 Elastic scattering cross section 3646 1451 48 Obtained by subtracting non-elastic cross sections from total 3646 1451 49 cross sections above 1 keV. A constant value of 6.2557 is 3646 1451 50 assumed below 1 keV. 3646 1451 51 3646 1451 52 MT= 3 Non-elastic cross section 3646 1451 53 Sum of partial non-elastic cross sections. 3646 1451 54 3646 1451 55 MT= 4,51-91 (n,n') cross section 3646 1451 56 Calculated with POD code /1/. 3646 1451 57 3646 1451 58 MT= 16 (n,2n) cross section 3646 1451 59 Calculated with POD code /1/. 3646 1451 60 3646 1451 61 MT= 17 (n,3n) cross section 3646 1451 62 Calculated with POD code /1/. 3646 1451 63 3646 1451 64 MT= 22 (n,na) cross section 3646 1451 65 Calculated with POD code /1/. 3646 1451 66 3646 1451 67 MT= 28 (n,np) cross section 3646 1451 68 Calculated with POD code /1/. 3646 1451 69 3646 1451 70 MT= 32 (n,nd) cross section 3646 1451 71 Calculated with POD code /1/. 3646 1451 72 3646 1451 73 MT=102 Capture cross section 3646 1451 74 Calculated with POD code /1/ above 1 keV. The 1/v form 3646 1451 75 was assumed below 1 keV, and the cross section was normalized 3646 1451 76 to 1.66 b at 0.0253 eV./2/ 3646 1451 77 3646 1451 78 MT=103 (n,p) cross section 3646 1451 79 Calculated with POD code /1/. 3646 1451 80 3646 1451 81 MT=104 (n,d) cross section 3646 1451 82 Calculated with POD code /1/. 3646 1451 83 3646 1451 84 MT=105 (n,t) cross section 3646 1451 85 Calculated with POD code /1/. 3646 1451 86 3646 1451 87 MT=106 (n,He3) cross section 3646 1451 88 Calculated with POD code /1/. 3646 1451 89 3646 1451 90 MT=107 (n,a) cross section 3646 1451 91 Calculated with POD code /1/. 3646 1451 92 3646 1451 93 MT=203 (n,xp) cross section 3646 1451 94 Calculated with POD code /1/. 3646 1451 95 3646 1451 96 MT=204 (n,xd) cross section 3646 1451 97 Calculated with POD code /1/. 3646 1451 98 3646 1451 99 MT=205 (n,xt) cross section 3646 1451 100 Calculated with POD code /1/. 3646 1451 101 3646 1451 102 MT=206 (n,xHe3) cross section 3646 1451 103 Calculated with POD code /1/. 3646 1451 104 3646 1451 105 MT=207 (n,xa) cross section 3646 1451 106 Calculated with POD code /1/. 3646 1451 107 3646 1451 108 MF= 4 Angular distributions of emitted neutrons 3646 1451 109 MT= 2 Elastic scattering 3646 1451 110 Calculated with POD code /1/. 3646 1451 111 3646 1451 112 MF= 6 Energy-angle distributions of emitted particles 3646 1451 113 MT= 16 (n,2n) reaction 3646 1451 114 Neutron spectra calculated with POD/1/. 3646 1451 115 3646 1451 116 MT= 17 (n,3n) reaction 3646 1451 117 Neutron spectra calculated with POD/1/. 3646 1451 118 3646 1451 119 MT= 22 (n,na) reaction 3646 1451 120 Neutron spectra calculated with POD/1/. 3646 1451 121 3646 1451 122 MT= 28 (n,np) reaction 3646 1451 123 Neutron spectra calculated with POD/1/. 3646 1451 124 3646 1451 125 MT= 32 (n,nd) reaction 3646 1451 126 Neutron spectra calculated with POD/1/. 3646 1451 127 3646 1451 128 MT= 51 (n,n') reaction 3646 1451 129 Neutron angular distributions calculated with POD/1/. 3646 1451 130 3646 1451 131 MT= 52 (n,n') reaction 3646 1451 132 Neutron angular distributions calculated with POD/1/. 3646 1451 133 3646 1451 134 MT= 53 (n,n') reaction 3646 1451 135 Neutron angular distributions calculated with POD/1/. 3646 1451 136 3646 1451 137 MT= 54 (n,n') reaction 3646 1451 138 Neutron angular distributions calculated with POD/1/. 3646 1451 139 3646 1451 140 MT= 55 (n,n') reaction 3646 1451 141 Neutron angular distributions calculated with POD/1/. 3646 1451 142 3646 1451 143 MT= 56 (n,n') reaction 3646 1451 144 Neutron angular distributions calculated with POD/1/. 3646 1451 145 3646 1451 146 MT= 57 (n,n') reaction 3646 1451 147 Neutron angular distributions calculated with POD/1/. 3646 1451 148 3646 1451 149 MT= 58 (n,n') reaction 3646 1451 150 Neutron angular distributions calculated with POD/1/. 3646 1451 151 3646 1451 152 MT= 59 (n,n') reaction 3646 1451 153 Neutron angular distributions calculated with POD/1/. 3646 1451 154 3646 1451 155 MT= 60 (n,n') reaction 3646 1451 156 Neutron angular distributions calculated with POD/1/. 3646 1451 157 3646 1451 158 MT= 61 (n,n') reaction 3646 1451 159 Neutron angular distributions calculated with POD/1/. 3646 1451 160 3646 1451 161 MT= 62 (n,n') reaction 3646 1451 162 Neutron angular distributions calculated with POD/1/. 3646 1451 163 3646 1451 164 MT= 63 (n,n') reaction 3646 1451 165 Neutron angular distributions calculated with POD/1/. 3646 1451 166 3646 1451 167 MT= 64 (n,n') reaction 3646 1451 168 Neutron angular distributions calculated with POD/1/. 3646 1451 169 3646 1451 170 MT= 65 (n,n') reaction 3646 1451 171 Neutron angular distributions calculated with POD/1/. 3646 1451 172 3646 1451 173 MT= 66 (n,n') reaction 3646 1451 174 Neutron angular distributions calculated with POD/1/. 3646 1451 175 3646 1451 176 MT= 67 (n,n') reaction 3646 1451 177 Neutron angular distributions calculated with POD/1/. 3646 1451 178 3646 1451 179 MT= 68 (n,n') reaction 3646 1451 180 Neutron angular distributions calculated with POD/1/. 3646 1451 181 3646 1451 182 MT= 69 (n,n') reaction 3646 1451 183 Neutron angular distributions calculated with POD/1/. 3646 1451 184 3646 1451 185 MT= 70 (n,n') reaction 3646 1451 186 Neutron angular distributions calculated with POD/1/. 3646 1451 187 3646 1451 188 MT= 71 (n,n') reaction 3646 1451 189 Neutron angular distributions calculated with POD/1/. 3646 1451 190 3646 1451 191 MT= 72 (n,n') reaction 3646 1451 192 Neutron angular distributions calculated with POD/1/. 3646 1451 193 3646 1451 194 MT= 73 (n,n') reaction 3646 1451 195 Neutron angular distributions calculated with POD/1/. 3646 1451 196 3646 1451 197 MT= 74 (n,n') reaction 3646 1451 198 Neutron angular distributions calculated with POD/1/. 3646 1451 199 3646 1451 200 MT= 75 (n,n') reaction 3646 1451 201 Neutron angular distributions calculated with POD/1/. 3646 1451 202 3646 1451 203 MT= 76 (n,n') reaction 3646 1451 204 Neutron angular distributions calculated with POD/1/. 3646 1451 205 3646 1451 206 MT= 77 (n,n') reaction 3646 1451 207 Neutron angular distributions calculated with POD/1/. 3646 1451 208 3646 1451 209 MT= 78 (n,n') reaction 3646 1451 210 Neutron angular distributions calculated with POD/1/. 3646 1451 211 3646 1451 212 MT= 79 (n,n') reaction 3646 1451 213 Neutron angular distributions calculated with POD/1/. 3646 1451 214 3646 1451 215 MT= 80 (n,n') reaction 3646 1451 216 Neutron angular distributions calculated with POD/1/. 3646 1451 217 3646 1451 218 MT= 81 (n,n') reaction 3646 1451 219 Neutron angular distributions calculated with POD/1/. 3646 1451 220 3646 1451 221 MT= 82 (n,n') reaction 3646 1451 222 Neutron angular distributions calculated with POD/1/. 3646 1451 223 3646 1451 224 MT= 91 (n,n') reaction 3646 1451 225 Neutron spectra calculated with POD/1/. 3646 1451 226 3646 1451 227 MT= 203 (n,xp) reaction 3646 1451 228 Proton spectra calculated with POD/1/. 3646 1451 229 3646 1451 230 MT= 204 (n,xd) reaction 3646 1451 231 Deuteron spectra calculated with POD/1/. 3646 1451 232 3646 1451 233 MT= 205 (n,xt) reaction 3646 1451 234 Triton spectra calculated with POD/1/. 3646 1451 235 3646 1451 236 MT= 206 (n,xHe3) reaction 3646 1451 237 He3 spectra calculated with POD/1/. 3646 1451 238 3646 1451 239 MT= 207 (n,xa) reaction 3646 1451 240 Alpha spectra calculated with POD/1/. 3646 1451 241 3646 1451 242 MF=12 Gamma-ray multiplicities 3646 1451 243 MT= 3 Non-elastic gamma emission 3646 1451 244 Calculated with POD code /1/. 3646 1451 245 3646 1451 246 MF=14 Gamma-ray angular distributions 3646 1451 247 MT= 3 Non-elastic gamma emission 3646 1451 248 Assumed to be isotropic. 3646 1451 249 3646 1451 250 MF=15 Gamma-ray spectra 3646 1451 251 MT= 3 Non-elastic gamma emission 3646 1451 252 Calculated with POD code /1/. 3646 1451 253 3646 1451 254 3646 1451 255 3646 1451 256 *************************************************************** 3646 1451 257 * Nuclear Model Calculations with POD Code /1/ * 3646 1451 258 *************************************************************** 3646 1451 259 1. Theoretical models 3646 1451 260 The POD code is based on the spherical optical model, the 3646 1451 261 distorted-wave Born approximaiton (DWBA), one-component exciton 3646 1451 262 preequilibrium model, and the Hauser-Feshbach-Moldauer statis- 3646 1451 263 tical model. With the preequilibrim model, semi-empirical 3646 1451 264 pickup and knockout process can be taken into account for 3646 1451 265 composite-particle emission. The gamma-ray emission from the 3646 1451 266 compound nucleus can be calculated within the framework of the 3646 1451 267 exciton model. The code is capable of reading in particle 3646 1451 268 transmission coefficients calculated by separate spherical or 3646 1451 269 coupled-channel optical model code. 3646 1451 270 3646 1451 271 2. Optical model parameters 3646 1451 272 Neutrons: 3646 1451 273 Coupled-channel optical model parameters /3/ 3646 1451 274 Protons: 3646 1451 275 Koning and Delaroche /4/ 3646 1451 276 Deuterons: 3646 1451 277 Lohr and Haeberli /5/ 3646 1451 278 Tritons: 3646 1451 279 Becchetti and Greenlees /6/ 3646 1451 280 He-3: 3646 1451 281 Becchetti and Greenlees /6/ 3646 1451 282 Alphas: 3646 1451 283 Lemos /7/ potentials modified by Arthur and Young /8/ 3646 1451 284 3646 1451 285 3. Level scheme of Kr- 85 3646 1451 286 ------------------------- 3646 1451 287 No. Ex(MeV) J PI 3646 1451 288 ------------------------- 3646 1451 289 0 0.00000 9/2 + 3646 1451 290 1 0.30487 1/2 - 3646 1451 291 2 1.10732 1/2 - 3646 1451 292 3 1.14073 5/2 + 3646 1451 293 4 1.16669 5/2 + 3646 1451 294 5 1.22398 5/2 - 3646 1451 295 6 1.34261 3/2 + 3646 1451 296 7 1.41657 5/2 + 3646 1451 297 8 1.43060 1/2 + 3646 1451 298 9 1.61160 11/2 + 3646 1451 299 10 1.84700 7/2 + 3646 1451 300 11 1.87352 5/2 + 3646 1451 301 12 1.93150 13/2 + 3646 1451 302 13 1.93883 3/2 - 3646 1451 303 14 1.99010 9/2 + 3646 1451 304 15 1.99180 17/2 + 3646 1451 305 16 2.00440 7/2 + 3646 1451 306 17 2.05510 3/2 + 3646 1451 307 18 2.11340 9/2 + 3646 1451 308 19 2.13510 9/2 + 3646 1451 309 20 2.13734 5/2 - 3646 1451 310 21 2.14490 7/2 + 3646 1451 311 22 2.23520 5/2 - 3646 1451 312 23 2.38350 7/2 + 3646 1451 313 24 2.39800 5/2 - 3646 1451 314 25 2.49790 9/2 - 3646 1451 315 26 2.51340 9/2 - 3646 1451 316 27 2.53430 5/2 - 3646 1451 317 28 2.57370 7/2 - 3646 1451 318 29 2.59300 5/2 - 3646 1451 319 30 2.60240 3/2 - 3646 1451 320 31 2.61790 5/2 - 3646 1451 321 32 2.63670 11/2 + 3646 1451 322 ------------------------- 3646 1451 323 Levels above 2.64670 MeV are assumed to be continuous. 3646 1451 324 3646 1451 325 4. Level density parameters 3646 1451 326 Energy-dependent parameters of Mengoni-Nakajima /9/ were used 3646 1451 327 ---------------------------------------------------------- 3646 1451 328 Nuclei a* Pair Esh T E0 Ematch Elv_max 3646 1451 329 1/MeV MeV MeV MeV MeV MeV MeV 3646 1451 330 ---------------------------------------------------------- 3646 1451 331 Kr- 86 11.310 2.588 -0.507 0.715 2.085 6.130 3.575 3646 1451 332 Kr- 85 11.890 1.302 0.718 0.695 0.285 5.433 2.637 3646 1451 333 Kr- 84 11.089 2.619 1.235 0.745 1.364 7.286 3.951 3646 1451 334 Kr- 83 11.668 1.317 2.381 0.710 -0.316 6.290 1.889 3646 1451 335 Br- 85 10.720 1.302 -0.138 0.819 0.183 6.155 1.944 3646 1451 336 Br- 84 11.060 0.000 0.608 0.898 -2.409 6.862 0.408 3646 1451 337 Br- 83 10.507 1.317 1.382 0.813 -0.276 6.734 2.134 3646 1451 338 Se- 83 12.088 1.317 0.801 0.772 -0.514 6.837 1.331 3646 1451 339 Se- 82 10.867 2.650 1.071 0.699 1.874 6.455 3.586 3646 1451 340 Se- 81 10.589 1.333 1.999 0.755 -0.063 6.204 2.253 3646 1451 341 ---------------------------------------------------------- 3646 1451 342 3646 1451 343 5. Gamma-ray strength functions 3646 1451 344 M1, E2: Standard Lorentzian (SLO) 3646 1451 345 E1 : Generalized Lorentzian (GLO) /10/ 3646 1451 346 3646 1451 347 6. Preequilibrium process 3646 1451 348 Preequilibrium is on for n, p, d, t, He-3, and alpha. 3646 1451 349 Preequilibrium capture is on. 3646 1451 350 3646 1451 351 References 3646 1451 352 1) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 3646 1451 353 2) Mughabghab, S.F.: "Atlas of Neutron Resonances", Elsevier 3646 1451 354 (2006). 3646 1451 355 3) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 3646 1451 356 4) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 3646 1451 357 5) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 3646 1451 358 6) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization 3646 1451 359 Phenomena in Nuclear Reactions," p.682, The University 3646 1451 360 of Wisconsin Press (1971). 3646 1451 361 7) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 3646 1451 362 8) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 3646 1451 363 9) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 3646 1451 364 (1994). 3646 1451 365 10) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990). 3646 1451 366 3646 1451 367 1 451 393 13646 1451 368 2 151 4 13646 1451 369 3 4 26 13646 1451 370 3 16 9 13646 1451 371 3 17 5 13646 1451 372 3 22 7 13646 1451 373 3 28 7 13646 1451 374 3 32 5 13646 1451 375 3 102 129 13646 1451 376 3 103 12 13646 1451 377 3 104 8 13646 1451 378 3 105 7 13646 1451 379 3 106 5 13646 1451 380 3 107 12 13646 1451 381 8 4 2 13646 1451 382 8 16 2 13646 1451 383 8 17 2 13646 1451 384 8 22 2 13646 1451 385 8 28 2 13646 1451 386 8 32 2 13646 1451 387 8 102 2 13646 1451 388 8 103 2 13646 1451 389 8 104 2 13646 1451 390 8 105 2 13646 1451 391 8 106 2 13646 1451 392 8 107 2 13646 1451 393 3646 1 099999 3646 0 0 0 3.608500+4 8.418309+1 0 0 1 03646 2151 1 3.608500+4 1.000000+0 0 0 1 03646 2151 2 1.000000+3 1.000000+6 0 0 0 03646 2151 3 4.500000+0 6.489700-1 0 0 0 03646 2151 4 3646 2 099999 3646 0 0 0 3.608500+4 8.418309+1 0 0 0 03646 3 4 1 0.000000+0-3.048710+5 0 0 1 693646 3 4 2 69 2 3646 3 4 3 3.084925+5 0.000000+0 4.000000+5 3.136000-3 5.000000+5 6.066000-33646 3 4 4 6.000000+5 9.687000-3 7.000000+5 1.362000-2 8.000000+5 1.798000-23646 3 4 5 9.000000+5 2.278000-2 1.000000+6 2.794000-2 1.120474+6 2.757376-23646 3 4 6 1.154281+6 2.791281-2 1.180549+6 3.613903-2 1.238519+6 7.189377-23646 3 4 7 1.358559+6 1.758960-1 1.433397+6 2.469895-1 1.447594+6 2.640103-13646 3 4 8 1.500000+6 3.274884-1 1.630744+6 3.632481-1 1.868940+6 6.264334-13646 3 4 9 1.895775+6 6.653365-1 1.954444+6 7.578652-1 1.961861+6 7.760671-13646 3 4 10 2.000000+6 8.711100-1 2.013740+6 8.730980-1 2.015460+6 8.737678-13646 3 4 11 2.028210+6 8.808405-1 2.079512+6 9.166867-1 2.138505+6 9.595526-13646 3 4 12 2.160463+6 9.811125-1 2.162729+6 9.839184-1 2.170379+6 9.938051-13646 3 4 13 2.261752+6 1.125381+0 2.411813+6 1.349610+0 2.426486+6 1.373422+03646 3 4 14 2.500000+6 1.496771+0 2.527572+6 1.495883+0 2.543256+6 1.497043+03646 3 4 15 2.564405+6 1.500863+0 2.604273+6 1.509119+0 2.623802+6 1.514347+03646 3 4 16 2.633314+6 1.517147+0 2.648998+6 1.521933+0 2.668021+6 1.528249+03646 3 4 17 2.678140+6 1.533625+0 3.000000+6 1.828959+0 3.500000+6 1.920402+03646 3 4 18 4.000000+6 1.922637+0 4.500000+6 1.891073+0 5.000000+6 1.842008+03646 3 4 19 5.500000+6 1.800691+0 6.000000+6 1.771917+0 6.500000+6 1.754729+03646 3 4 20 7.000000+6 1.746424+0 7.500000+6 1.737030+0 8.000000+6 1.694234+03646 3 4 21 8.500000+6 1.617176+0 9.000000+6 1.498536+0 9.500000+6 1.370643+03646 3 4 22 1.000000+7 1.242704+0 1.100000+7 9.437944-1 1.200000+7 6.558626-13646 3 4 23 1.300000+7 4.817035-1 1.400000+7 3.819709-1 1.450000+7 3.476383-13646 3 4 24 1.500000+7 3.219340-1 1.600000+7 2.832462-1 1.700000+7 2.552734-13646 3 4 25 1.800000+7 2.337381-1 1.900000+7 2.162190-1 2.000000+7 2.014227-13646 3 4 26 3646 3 099999 3.608500+4 8.418309+1 0 0 0 03646 3 16 1 -7.120593+6-7.120593+6 0 0 1 183646 3 16 2 18 2 3646 3 16 3 7.205178+6 0.000000+0 7.500000+6 5.260000-3 8.000000+6 4.625000-23646 3 16 4 8.500000+6 1.206000-1 9.000000+6 2.370000-1 9.500000+6 3.604000-13646 3 16 5 1.000000+7 4.851000-1 1.100000+7 7.746000-1 1.200000+7 1.051000+03646 3 16 6 1.300000+7 1.211000+0 1.400000+7 1.292000+0 1.450000+7 1.315000+03646 3 16 7 1.500000+7 1.330000+0 1.600000+7 1.344000+0 1.700000+7 1.350000+03646 3 16 8 1.800000+7 1.352000+0 1.900000+7 1.336000+0 2.000000+7 1.254000+03646 3 16 9 3646 3 099999 3.608500+4 8.418309+1 0 0 0 03646 3 17 1 -1.764119+7-1.764119+7 0 0 1 43646 3 17 2 4 2 3646 3 17 3 1.785075+7 0.000000+0 1.800000+7 0.000000+0 1.900000+7 1.593000-23646 3 17 4 2.000000+7 9.616000-2 3646 3 17 5 3646 3 099999 3.608500+4 8.418309+1 0 0 0 03646 3 22 1 -7.515664+6-7.515664+6 0 0 1 103646 3 22 2 10 2 3646 3 22 3 7.604941+6 0.000000+0 1.300000+7 0.000000+0 1.400000+7 7.231000-83646 3 22 4 1.450000+7 4.163000-7 1.500000+7 1.678000-6 1.600000+7 1.152000-53646 3 22 5 1.700000+7 5.009000-5 1.800000+7 1.511000-4 1.900000+7 3.309000-43646 3 22 6 2.000000+7 5.706000-4 3646 3 22 7 3646 3 099999 3.608500+4 8.418309+1 0 0 0 03646 3 28 1 -1.096990+7-1.096990+7 0 0 1 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