JENDL-5 (Neutron sublibrary (activation cs)) Ac-227 0 0 0 0 8.922700+4 2.250770+2 0 0 6 18931 1451 1 0.000000+0 1.000000+0 0 0 0 68931 1451 2 1.000000+0 2.000000+7 0 0 10 58931 1451 3 2.936000+2 0.000000+0 4 0 346 148931 1451 4 89-Ac-227 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 8931 1451 5 DIST-DEC21 20100304 8931 1451 6 ----JENDL-5 MATERIAL 8931 8931 1451 7 -----INCIDENT NEUTRON DATA 8931 1451 8 ------ENDF-6 FORMAT 8931 1451 9 8931 1451 10 History 8931 1451 11 07-10 Theoretical calculation was performed with CCONE code. 8931 1451 12 Data were compiled as JENDL/AC-2008/1/. 8931 1451 13 10-02 Data of prompt gamma rays due to fission were given. 8931 1451 14 10-03 Covariance data were given. 8931 1451 15 21-11 revised by O.Iwamoto 8931 1451 16 (MF3/MT19-21,38) deleted 8931 1451 17 (MF8/MT4,16-18,37,102) added 8931 1451 18 8931 1451 19 8931 1451 20 MF=1 General information 8931 1451 21 MT=452 Number of Neutrons per fission 8931 1451 22 Sum of MT's=455 and 456. 8931 1451 23 8931 1451 24 MT=455 Delayed neutron data 8931 1451 25 Estimated from systematics by Tuttle/2/, Benedetti et al./3/ 8931 1451 26 and Waldo et al./4/ 8931 1451 27 8931 1451 28 MT=456 Number of prompt neutrons per fission 8931 1451 29 Estimated from Howerton's systematics/5/. 8931 1451 30 8931 1451 31 8931 1451 32 MF= 2 Resonance parameters 8931 1451 33 MT=151 8931 1451 34 No resonance parameters are given. 8931 1451 35 8931 1451 36 8931 1451 37 Thermal cross sections and resonance integrals (at 300K) 8931 1451 38 ------------------------------------------------------- 8931 1451 39 0.0253 eV reson. integ.(*) 8931 1451 40 (barns) (barns) 8931 1451 41 ------------------------------------------------------- 8931 1451 42 total 813.1 8931 1451 43 elastic 12.53 8931 1451 44 fission 0.0001 0.057 8931 1451 45 capture 800.3 1020 8931 1451 46 ------------------------------------------------------- 8931 1451 47 (*) In the energy range from 0.5 eV to 10 MeV. 8931 1451 48 8931 1451 49 8931 1451 50 MF= 3 Neutron cross sections 8931 1451 51 Below 0.6 eV: 8931 1451 52 * Elastic scattering cross section is 12.5b calculated from 8931 1451 53 scattering radius of 9.962 fm/6/. 8931 1451 54 * Fission cross section is in the 1/v shape. 8931 1451 55 1 mb at 0.0253 eV was estimated from the experimental 8931 1451 56 data of < 0.35 mb/7/. 8931 1451 57 * Capture cross section is in the 1/v shape. 8931 1451 58 Cross section of 800 b at 0.0253 eV was an average value of 8931 1451 59 experimental data of Monsecour and de Begge/8/ and 8931 1451 60 Cabell/9/. 8931 1451 61 8931 1451 62 Above 0.3 eV: 8931 1451 63 Cross sections were calculated with CCONE code/6/, except 8931 1451 64 for the elastic scattering (MT=2) and fission cross sections 8931 1451 65 (MT's=18, 19). 8931 1451 66 8931 1451 67 MT=1 Total cross section 8931 1451 68 The cross section was calculated with CC OMP of Soukhovitskii 8931 1451 69 et al./10/. 8931 1451 70 8931 1451 71 MT= 2 Elastic scattering cross section 8931 1451 72 Calculated as total - non-elastic scattering cross sections. 8931 1451 73 8931 1451 74 MT=18,19 Fission cross section, (n,f) cross section 8931 1451 75 Shape of 1/v was assumed up to 6.5 eV. 8931 1451 76 From 6.5 eV to 100 keV, a constant value of 6 micro-b was 8931 1451 77 assumed. 8931 1451 78 Above 170 keV, CCONE calculation was adopted. 8931 1451 79 Experimental data of Kuks et al./11/ were used to adjust 8931 1451 80 parameters of CCONE code. 8931 1451 81 8931 1451 82 8931 1451 83 MF= 4 Angular distributions of secondary neutrons 8931 1451 84 MT=2 Elastic scattering 8931 1451 85 Calculated with CCONE code/6/. 8931 1451 86 8931 1451 87 MT=18 Fission 8931 1451 88 Isotropic distributions in the laboratory system were assumed.8931 1451 89 8931 1451 90 8931 1451 91 MF= 5 Energy distributions of secondary neutrons 8931 1451 92 MT=18 Prompt neutrons 8931 1451 93 Calculated with CCONE code/6/. 8931 1451 94 8931 1451 95 8931 1451 96 MF= 6 Energy-angle distributions 8931 1451 97 Calculated with CCONE code/6/. 8931 1451 98 Distributions from fission (MT=18) are not included. 8931 1451 99 8931 1451 100 8931 1451 101 MF=12 Photon production multiplicities 8931 1451 102 MT=18 Fission 8931 1451 103 Calculated from the total energy released by the prompt 8931 1451 104 gamma-rays due to fission which was estimated from its 8931 1451 105 systematics, and the average energy of gamma-rays. 8931 1451 106 8931 1451 107 8931 1451 108 MF=14 Photon angular distributions 8931 1451 109 MT=18 Fission 8931 1451 110 Isotoropic distributions were assumed. 8931 1451 111 8931 1451 112 8931 1451 113 MF=15 Continuous photon energy spectra 8931 1451 114 MT=18 Fission 8931 1451 115 Experimental data measured by Verbinski et al./12/ for 8931 1451 116 U-235 thermal fission were adopted. 8931 1451 117 8931 1451 118 8931 1451 119 MF=31 Covariances of average number of neutrons per fission 8931 1451 120 MT=452 Number of neutrons per fission 8931 1451 121 Sum of covariances for MT=455 and MT=456. 8931 1451 122 8931 1451 123 MT=455 8931 1451 124 Error of 15% was assumed. 8931 1451 125 8931 1451 126 MT=456 8931 1451 127 Covariance was obtained by fitting a linear function to the 8931 1451 128 at 0.0 and 5.0 MeV with an uncertainty of 5%. 8931 1451 129 8931 1451 130 8931 1451 131 MF=33 Covariances of neutron cross sections 8931 1451 132 Covariances were given to all the cross sections by using 8931 1451 133 KALMAN code/13/ and the covariances of model parameters 8931 1451 134 used in the cross-section calculations. 8931 1451 135 8931 1451 136 Covariances of the fission cross section were determined from 8931 1451 137 experimental data. 8931 1451 138 8931 1451 139 For the following cross sections, standard deviations in the 8931 1451 140 energy region below 0.6 eV were assumed as follows: 8931 1451 141 8931 1451 142 Total 2.9 % 8931 1451 143 Elastic scattering 50 % 8931 1451 144 Fission 50 % 8931 1451 145 Capture 2.8 % estimated from experimental data 8931 1451 146 8931 1451 147 8931 1451 148 MF=34 Covariances for Angular Distributions 8931 1451 149 MT=2 Elastic scattering 8931 1451 150 Covariances were given only to P1 components. 8931 1451 151 8931 1451 152 8931 1451 153 MF=35 Covariances for Energy Distributions 8931 1451 154 MT=18 Fission spectra 8931 1451 155 Estimated with CCONE and KALMAN codes. 8931 1451 156 8931 1451 157 8931 1451 158 ***************************************************************** 8931 1451 159 Calculation with CCONE code 8931 1451 160 ***************************************************************** 8931 1451 161 8931 1451 162 Models and parameters used in the CCONE/6/ calculation 8931 1451 163 1) Coupled channel optical model 8931 1451 164 Levels in the rotational band were included. Optical model 8931 1451 165 potential and coupled levels are shown in Table 1. 8931 1451 166 8931 1451 167 2) Two-component exciton model/14/ 8931 1451 168 * Global parametrization of Koning-Duijvestijn/15/ 8931 1451 169 was used. 8931 1451 170 * Gamma emission channel/16/ was added to simulate direct 8931 1451 171 and semi-direct capture reaction. 8931 1451 172 8931 1451 173 3) Hauser-Feshbach statistical model 8931 1451 174 * Moldauer width fluctuation correction/17/ was included. 8931 1451 175 * Neutron, gamma and fission decay channel were included. 8931 1451 176 * Transmission coefficients of neutrons were taken from 8931 1451 177 coupled channel calculation in Table 1. 8931 1451 178 * The level scheme of the target is shown in Table 2. 8931 1451 179 * Level density formula of constant temperature and Fermi-gas 8931 1451 180 model were used with shell energy correction and collective 8931 1451 181 enhancement factor. Parameters are shown in Table 3. 8931 1451 182 * Fission channel: 8931 1451 183 Double humped fission barriers were assumed. 8931 1451 184 Fission barrier penetrabilities were calculated with 8931 1451 185 Hill-Wheler formula/18/. Fission barrier parameters were 8931 1451 186 shown in Table 4. Transition state model was used and 8931 1451 187 continuum levels are assumed above the saddles. The level 8931 1451 188 density parameters for inner and outer saddles are shown in 8931 1451 189 Tables 5 and 6, respectively. 8931 1451 190 * Gamma-ray strength function of Kopecky et al/19/,/20/ 8931 1451 191 was used. The prameters are shown in Table 7. 8931 1451 192 8931 1451 193 8931 1451 194 ------------------------------------------------------------------8931 1451 195 Tables 8931 1451 196 ------------------------------------------------------------------8931 1451 197 8931 1451 198 Table 1. Coupled channel calculation 8931 1451 199 -------------------------------------------------- 8931 1451 200 * rigid rotor model was applied 8931 1451 201 * coupled levels = 0,2,4,7,11 (see Table 2) 8931 1451 202 * optical potential parameters /10/ 8931 1451 203 Volume: 8931 1451 204 V_0 = 49.97 MeV 8931 1451 205 lambda_HF = 0.01004 1/MeV 8931 1451 206 C_viso = 15.9 MeV 8931 1451 207 A_v = 12.04 MeV 8931 1451 208 B_v = 81.36 MeV 8931 1451 209 E_a = 385 MeV 8931 1451 210 r_v = 1.2568 fm 8931 1451 211 a_v = 0.633 fm 8931 1451 212 Surface: 8931 1451 213 W_0 = 17.2 MeV 8931 1451 214 B_s = 11.19 MeV 8931 1451 215 C_s = 0.01361 1/MeV 8931 1451 216 C_wiso = 23.5 MeV 8931 1451 217 r_s = 1.1803 fm 8931 1451 218 a_s = 0.601 fm 8931 1451 219 Spin-orbit: 8931 1451 220 V_so = 5.75 MeV 8931 1451 221 lambda_so = 0.005 1/MeV 8931 1451 222 W_so = -3.1 MeV 8931 1451 223 B_so = 160 MeV 8931 1451 224 r_so = 1.1214 fm 8931 1451 225 a_so = 0.59 fm 8931 1451 226 Coulomb: 8931 1451 227 C_coul = 1.3 8931 1451 228 r_c = 1.2452 fm 8931 1451 229 a_c = 0.545 fm 8931 1451 230 Deformation: 8931 1451 231 beta_2 = 0.213 8931 1451 232 beta_4 = 0.066 8931 1451 233 beta_6 = 0.0015 8931 1451 234 8931 1451 235 * Calculated strength function 8931 1451 236 S0= 0.98e-4 S1= 2.28e-4 R'= 9.96 fm (En=1 keV) 8931 1451 237 -------------------------------------------------- 8931 1451 238 8931 1451 239 Table 2. Level Scheme of Ac-227 8931 1451 240 ------------------- 8931 1451 241 No. Ex(MeV) J PI 8931 1451 242 ------------------- 8931 1451 243 0 0.00000 3/2 - * 8931 1451 244 1 0.02737 3/2 + 8931 1451 245 2 0.02998 5/2 - * 8931 1451 246 3 0.04635 5/2 + 8931 1451 247 4 0.07414 7/2 - * 8931 1451 248 5 0.08455 7/2 + 8931 1451 249 6 0.10994 9/2 + 8931 1451 250 7 0.12686 9/2 - * 8931 1451 251 8 0.14800 5/2 + 8931 1451 252 9 0.16000 7/2 - 8931 1451 253 10 0.18732 11/2 + 8931 1451 254 11 0.19871 11/2 - * 8931 1451 255 12 0.21078 13/2 + 8931 1451 256 13 0.22700 9/2 + 8931 1451 257 14 0.24900 15/2 + 8931 1451 258 15 0.27129 13/2 - 8931 1451 259 16 0.27314 5/2 - 8931 1451 260 17 0.30473 5/2 + 8931 1451 261 18 0.31600 7/2 - 8931 1451 262 19 0.33004 3/2 - 8931 1451 263 20 0.34200 7/2 + 8931 1451 264 ------------------- 8931 1451 265 *) Coupled levels in CC calculation 8931 1451 266 8931 1451 267 Table 3. Level density parameters 8931 1451 268 -------------------------------------------------------- 8931 1451 269 Nuclide a* Pair Eshell T E0 Ematch 8931 1451 270 1/MeV MeV MeV MeV MeV MeV 8931 1451 271 -------------------------------------------------------- 8931 1451 272 Ac-228 17.7035 0.0000 3.5524 0.3477 -1.2833 1.7974 8931 1451 273 Ac-227 17.6369 0.7965 3.3377 0.4083 -1.1126 3.3578 8931 1451 274 Ac-226 17.5702 0.0000 3.0355 0.3357 -1.1051 1.5780 8931 1451 275 Ac-225 17.5034 0.8000 2.9322 0.4278 -1.2611 3.5537 8931 1451 276 Ac-224 17.4367 0.0000 2.4959 0.3776 -1.4315 1.9979 8931 1451 277 -------------------------------------------------------- 8931 1451 278 8931 1451 279 Table 4. Fission barrier parameters 8931 1451 280 ---------------------------------------- 8931 1451 281 Nuclide V_A hw_A V_B hw_B 8931 1451 282 MeV MeV MeV MeV 8931 1451 283 ---------------------------------------- 8931 1451 284 Ac-228 7.000 0.800 7.100 0.900 8931 1451 285 Ac-227 7.000 0.800 7.100 0.930 8931 1451 286 Ac-226 6.500 0.800 6.900 0.900 8931 1451 287 Ac-225 7.000 0.800 7.100 0.930 8931 1451 288 Ac-224 7.000 0.800 7.100 0.900 8931 1451 289 ---------------------------------------- 8931 1451 290 8931 1451 291 Table 5. Level density above inner saddle 8931 1451 292 -------------------------------------------------------- 8931 1451 293 Nuclide a* Pair Eshell T E0 Ematch 8931 1451 294 1/MeV MeV MeV MeV MeV MeV 8931 1451 295 -------------------------------------------------------- 8931 1451 296 Ac-228 18.5887 0.0000 2.6000 0.3469 -2.4547 2.0000 8931 1451 297 Ac-227 19.4006 0.9292 2.6000 0.3387 -1.4940 2.9292 8931 1451 298 Ac-226 18.4487 0.0000 2.6000 0.3484 -2.4548 2.0000 8931 1451 299 Ac-225 18.3786 0.9333 2.6000 0.3491 -1.5215 2.9333 8931 1451 300 Ac-224 18.3085 0.0000 2.6000 0.3498 -2.4549 2.0000 8931 1451 301 -------------------------------------------------------- 8931 1451 302 8931 1451 303 Table 6. Level density above outer saddle 8931 1451 304 -------------------------------------------------------- 8931 1451 305 Nuclide a* Pair Eshell T E0 Ematch 8931 1451 306 1/MeV MeV MeV MeV MeV MeV 8931 1451 307 -------------------------------------------------------- 8931 1451 308 Ac-228 18.5887 0.0000 -0.3600 0.3970 -1.7115 2.0000 8931 1451 309 Ac-227 19.4006 0.9292 -0.4000 0.3875 -0.7697 2.9292 8931 1451 310 Ac-226 18.4487 0.0000 -0.4400 0.3999 -1.7104 2.0000 8931 1451 311 Ac-225 18.3786 0.9333 -0.4800 0.4014 -0.7766 2.9333 8931 1451 312 Ac-224 18.3085 0.0000 -0.5200 0.4028 -1.7094 2.0000 8931 1451 313 -------------------------------------------------------- 8931 1451 314 8931 1451 315 Table 7. Gamma-ray strength function for Ac-228 8931 1451 316 -------------------------------------------------------- 8931 1451 317 K0 = 1.503 E0 = 4.500 (MeV) 8931 1451 318 * E1: ER = 11.03 (MeV) EG = 2.71 (MeV) SIG = 302.00 (mb) 8931 1451 319 ER = 13.87 (MeV) EG = 4.77 (MeV) SIG = 449.00 (mb) 8931 1451 320 * M1: ER = 6.71 (MeV) EG = 4.00 (MeV) SIG = 2.82 (mb) 8931 1451 321 * E2: ER = 10.31 (MeV) EG = 3.37 (MeV) SIG = 6.13 (mb) 8931 1451 322 -------------------------------------------------------- 8931 1451 323 8931 1451 324 8931 1451 325 References 8931 1451 326 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 8931 1451 327 2) R.J.Tuttle: INDC(NDS)-107/G+Special, p.29 (1979). 8931 1451 328 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 8931 1451 329 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 8931 1451 330 5) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 8931 1451 331 6) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 8931 1451 332 7) P.del Marmol et al.: J. Inorg. Nucl. Chem., 35, 4323 (1973). 8931 1451 333 8) M.Monsecour, P.de Regge: J. Inorg. Nucl. Chem., 37, 1841 8931 1451 334 (1975). 8931 1451 335 9) M.J.Cabell: Can. J. Chem., 37, 1094 (1959). 8931 1451 336 10) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 8931 1451 337 11) I.M.Kuks et al.: Prog.Rep. Yaderno-Fizicheskie Issledovaniya 8931 1451 338 Reports No.26, p.46 (1978). 8931 1451 339 12) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 8931 1451 340 13) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 8931 1451 341 Japanese. 8931 1451 342 14) C.Kalbach: Phys. Rev. C33, 818 (1986). 8931 1451 343 15) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 8931 1451 344 16) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 8931 1451 345 17) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 8931 1451 346 18) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 8931 1451 347 19) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 8931 1451 348 20) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 8931 1451 349 8931 1451 350 1 451 364 18931 1451 351 2 151 4 18931 1451 352 3 4 33 18931 1451 353 3 16 13 18931 1451 354 3 17 9 18931 1451 355 3 18 217 18931 1451 356 3 37 4 18931 1451 357 3 102 160 18931 1451 358 8 4 2 18931 1451 359 8 16 2 18931 1451 360 8 17 2 18931 1451 361 8 18 2 18931 1451 362 8 37 2 18931 1451 363 8 102 2 18931 1451 364 8931 1 099999 8931 0 0 0 8.922700+4 2.250770+2 0 0 1 08931 2151 1 8.922700+4 1.000000+0 0 0 1 08931 2151 2 1.000000-5 6.000000-1 0 0 0 08931 2151 3 1.500000+0 9.962000-1 0 0 0 08931 2151 4 8931 2 099999 8931 0 0 0 8.922700+4 2.250770+2 0 0 0 08931 3 4 1 0.000000+0-2.737000+4 0 0 1 908931 3 4 2 90 2 8931 3 4 3 2.749160+4 0.000000+0 3.000000+4 1.146220-1 3.011320+4 1.167970-18931 3 4 4 4.655590+4 5.016630-1 5.000000+4 6.300570-1 7.000000+4 9.025520-18931 3 4 5 7.446940+4 9.401570-1 8.492560+4 1.030290+0 1.000000+5 1.186659+08931 3 4 6 1.061510+5 1.210856+0 1.104280+5 1.227696+0 1.200000+5 1.263376+08931 3 4 7 1.274240+5 1.290517+0 1.400000+5 1.336530+0 1.486580+5 1.368818+08931 3 4 8 1.607110+5 1.450352+0 1.700000+5 1.502733+0 1.881520+5 1.604737+08931 3 4 9 1.995930+5 1.671067+0 2.000000+5 1.673456+0 2.117160+5 1.689999+08931 3 4 10 2.280080+5 1.717301+0 2.280090+5 1.717303+0 2.500000+5 1.758440+08931 3 4 11 2.501060+5 1.758655+0 2.724950+5 1.809249+0 2.743540+5 1.813925+08931 3 4 12 3.000000+5 1.898628+0 3.060840+5 1.898241+0 3.174040+5 1.909573+08931 3 4 13 3.315060+5 1.919878+0 3.435190+5 1.937813+0 3.435200+5 1.937815+08931 3 4 14 4.000000+5 2.027430+0 5.000000+5 2.273087+0 6.000000+5 2.366537+08931 3 4 15 7.000000+5 2.515660+0 8.000000+5 2.596671+0 9.000000+5 2.690006+08931 3 4 16 1.000000+6 2.796856+0 1.100000+6 2.882745+0 1.200000+6 2.966311+08931 3 4 17 1.300000+6 3.048793+0 1.400000+6 3.124564+0 1.500000+6 3.198138+08931 3 4 18 1.600000+6 3.264638+0 1.700000+6 3.324664+0 1.800000+6 3.378106+08931 3 4 19 1.900000+6 3.421858+0 2.000000+6 3.459730+0 2.100000+6 3.486197+08931 3 4 20 2.200000+6 3.508092+0 2.400000+6 3.535538+0 2.600000+6 3.546795+08931 3 4 21 2.800000+6 3.544862+0 3.000000+6 3.536828+0 3.500000+6 3.494229+08931 3 4 22 4.000000+6 3.446436+0 4.500000+6 3.371256+0 5.000000+6 3.322072+08931 3 4 23 5.500000+6 3.252397+0 6.000000+6 3.218356+0 6.500000+6 3.179376+08931 3 4 24 7.000000+6 3.028517+0 7.500000+6 2.479582+0 8.000000+6 1.921633+08931 3 4 25 8.500000+6 1.474056+0 9.000000+6 1.156719+0 9.500000+6 9.379334-18931 3 4 26 1.000000+7 7.925432-1 1.050000+7 6.968001-1 1.100000+7 6.271123-18931 3 4 27 1.150000+7 5.750340-1 1.200000+7 5.402132-1 1.250000+7 5.118998-18931 3 4 28 1.300000+7 4.870055-1 1.350000+7 4.654487-1 1.400000+7 4.450637-18931 3 4 29 1.450000+7 4.311594-1 1.500000+7 4.131397-1 1.550000+7 4.005955-18931 3 4 30 1.600000+7 3.835128-1 1.650000+7 3.723178-1 1.700000+7 3.608053-18931 3 4 31 1.750000+7 3.500814-1 1.800000+7 3.393760-1 1.850000+7 3.294004-18931 3 4 32 1.900000+7 3.194911-1 1.950000+7 3.101668-1 2.000000+7 3.007480-18931 3 4 33 8931 3 099999 8.922700+4 2.250770+2 0 0 0 08931 3 16 1 -6.530590+6-6.530590+6 0 0 1 288931 3 16 2 28 2 8931 3 16 3 6.559600+6 0.000000+0 7.000000+6 1.367300-1 7.500000+6 6.605840-18931 3 16 4 8.000000+6 1.210600+0 8.500000+6 1.640120+0 9.000000+6 1.951560+08931 3 16 5 9.500000+6 2.156020+0 1.000000+7 2.291520+0 1.050000+7 2.372620+08931 3 16 6 1.100000+7 2.428100+0 1.150000+7 2.465470+0 1.200000+7 2.484290+08931 3 16 7 1.250000+7 2.496120+0 1.300000+7 2.467620+0 1.350000+7 2.353640+08931 3 16 8 1.400000+7 2.169500+0 1.450000+7 1.933220+0 1.500000+7 1.679630+08931 3 16 9 1.550000+7 1.425630+0 1.600000+7 1.244160+0 1.650000+7 1.080270+08931 3 16 10 1.700000+7 9.410270-1 1.750000+7 7.970530-1 1.800000+7 7.311030-18931 3 16 11 1.850000+7 6.545520-1 1.900000+7 5.919070-1 1.950000+7 5.412890-18931 3 16 12 2.000000+7 5.133570-1 8931 3 16 13 8931 3 099999 8.922700+4 2.250770+2 0 0 0 08931 3 17 1 -1.192990+7-1.192990+7 0 0 1 178931 3 17 2 17 2 8931 3 17 3 1.198290+7 0.000000+0 1.250000+7 2.378690-3 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