JENDL-5 (Neutron sublibrary (activation cs)) Th-228 0 0 0 0 9.022800+4 2.260700+2 0 0 6 19028 1451 1 0.000000+0 1.000000+0 0 0 0 69028 1451 2 1.000000+0 2.000000+7 0 0 10 59028 1451 3 2.936000+2 0.000000+0 4 0 364 129028 1451 4 90-Th-228 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9028 1451 5 DIST-DEC21 20100319 9028 1451 6 ----JENDL-5 MATERIAL 9028 9028 1451 7 -----INCIDENT NEUTRON DATA 9028 1451 8 ------ENDF-6 FORMAT 9028 1451 9 9028 1451 10 History 9028 1451 11 07-06 Theoretical calculation was performed with CCONE code. 9028 1451 12 07-07 Data were compiled as JENDL/AC-2008/1/. 9028 1451 13 10-02 Data of prompt gamma rays due to fission were given. 9028 1451 14 Nu-total, nu-p and nu-d were revised. 9028 1451 15 10-03 Covariance data were given. 9028 1451 16 9028 1451 17 21-11 revised by O.Iwamoto 9028 1451 18 (MF3/MT19-21,38) deleted 9028 1451 19 (MF8/MT16-18,102) JENDL/AD-2017 adopted 9028 1451 20 (MF8/MT4) added 9028 1451 21 9028 1451 22 MF=1 General information 9028 1451 23 MT=452 Number of Neutrons per fission 9028 1451 24 Sum of MT's=455 and 456. 9028 1451 25 9028 1451 26 MT=455 Delayed neutron data 9028 1451 27 Average values of systematics of Tuttle/2/, Benedetti et 9028 1451 28 al./3/ and Waldo et al./4/ were adopted. 9028 1451 29 9028 1451 30 MT=456 Number of prompt neutrons per fission 9028 1451 31 Based on the semi-empirical formula of Ohsawa/5/. 9028 1451 32 9028 1451 33 9028 1451 34 MF= 2 Resonance parameters 9028 1451 35 MT=151 9028 1451 36 Resolved resonance parameters (MLBW: 10e-5 - 13 eV) 9028 1451 37 Parameters of JENDL-3.3 which were based on the data obtained 9028 1451 38 by Simpson et al./6/ were adopted. A negative resonance 9028 1451 39 recommended by Mughabghab/7/ was added so as to reproduce 9028 1451 40 the thermal cross sections. 9028 1451 41 Fission widths were ignored. The fission cross section is 9028 1451 42 given as background cross sections. 9028 1451 43 9028 1451 44 Unresolved resonance parameters (13 eV - 70 keV) 9028 1451 45 Parameters (URP) were determined with ASREP code /8/ so as to 9028 1451 46 reproduce the cross sections in this energy region. URP are 9028 1451 47 used only for self-shielding calculations. 9028 1451 48 9028 1451 49 Thermal cross sections and resonance integrals (at 300K) 9028 1451 50 ------------------------------------------------------- 9028 1451 51 0.0253 eV reson. integ.(*) 9028 1451 52 (barns) (barns) 9028 1451 53 ------------------------------------------------------- 9028 1451 54 total 154.35 9028 1451 55 elastic 31.30 9028 1451 56 fission 0.15 1.38 9028 1451 57 capture 122.90 1120 9028 1451 58 ------------------------------------------------------- 9028 1451 59 (*) In the energy range from 0.5 eV to 10 MeV. 9028 1451 60 9028 1451 61 9028 1451 62 MF= 3 Neutron cross sections 9028 1451 63 Cross sections except for the elastic scattering (MT=2) and 9028 1451 64 fission cross sections (MT=18,19) below 100 keV were calculated 9028 1451 65 with CCONE code/9/. 9028 1451 66 9028 1451 67 MT= 1 Total cross section 9028 1451 68 The cross section was calculated with CC OMP of Soukhovitskii 9028 1451 69 et al./10/. 9028 1451 70 9028 1451 71 MT= 2 Elastic scattering cross section 9028 1451 72 Calculated as total - non-elastic scattering cross sections. 9028 1451 73 9028 1451 74 MT=18,19 Fission cross section, (n,f) cross section 9028 1451 75 Below 4.5 keV, 1/v shape was assumed. The cross section at 9028 1451 76 0.0253 eV was assumed to be 0.15 b which was determined from 9028 1451 77 "< 0.3 b" recommended by Mughabghab/7/. 9028 1451 78 From 4.5 to 100 keV, assumed to be 0.34 mb. 9028 1451 79 From 100keV to 20 MeV, calculated with CCONE code/9/. 9028 1451 80 9028 1451 81 The fission cross section measured by James et al./11/ were 9028 1451 82 used to adjust parameters of CCONE code. 9028 1451 83 9028 1451 84 9028 1451 85 MF= 4 Angular distributions of secondary neutrons 9028 1451 86 MT=2 Elastic scattering 9028 1451 87 Calculated with CCONE code/9/. 9028 1451 88 9028 1451 89 MT=18 Fission 9028 1451 90 Isotropic distributions in the laboratory system were assumed.9028 1451 91 9028 1451 92 9028 1451 93 MF= 5 Energy distributions of secondary neutrons 9028 1451 94 MT=18 Prompt neutrons 9028 1451 95 Calculated with CCONE code/9/. 9028 1451 96 9028 1451 97 9028 1451 98 MF= 6 Energy-angle distributions 9028 1451 99 Calculated with CCONE code/9/. 9028 1451 100 Distributions from fission (MT=18) are not included. 9028 1451 101 9028 1451 102 9028 1451 103 MF=12 Photon production multiplicities 9028 1451 104 MT=18 Fission 9028 1451 105 Calculated from the total energy released by the prompt 9028 1451 106 gamma-rays due to fission which was estimated from its 9028 1451 107 systematics, and the average energy of gamma-rays. 9028 1451 108 9028 1451 109 9028 1451 110 MF=14 Photon angular distributions 9028 1451 111 MT=18 Fission 9028 1451 112 Isotoropic distributions were assumed. 9028 1451 113 9028 1451 114 9028 1451 115 MF=15 Continuous photon energy spectra 9028 1451 116 MT=18 Fission 9028 1451 117 Experimental data measured by Verbinski et al./12/ for 9028 1451 118 U-235 thermal fission were adopted. 9028 1451 119 9028 1451 120 9028 1451 121 MF=31 Covariances of average number of neutrons per fission 9028 1451 122 MT=452 Number of neutrons per fission 9028 1451 123 Sum of covariances for MT=455 and MT=456. 9028 1451 124 9028 1451 125 MT=455 9028 1451 126 Error of 15% was assumed. 9028 1451 127 9028 1451 128 MT=456 9028 1451 129 Covariance was obtained by fitting a linear function to the 9028 1451 130 at 0.0 and 5.0 MeV with an uncertainty of 5%. 9028 1451 131 9028 1451 132 9028 1451 133 MF=32 Covariances of resonance parameters 9028 1451 134 MT=151 9028 1451 135 Format of LCOMP=0 was adopted. 9028 1451 136 Uncertainties of parameters were taken from Mughabghab /7/ 9028 1451 137 and Simpson et al./6/ For the parameters without any 9028 1451 138 information on uncertainty, unceratainties of 0.1% and 10% 9028 1451 139 were assumed to resonance energies and resonance widths, 9028 1451 140 respectively. 9028 1451 141 9028 1451 142 9028 1451 143 MF=33 Covariances of neutron cross sections 9028 1451 144 Covariances were given to all the cross sections by using 9028 1451 145 KALMAN code/13/ and the covariances of model parameters 9028 1451 146 used in the cross-section calculations. 9028 1451 147 9028 1451 148 In the resolved resonance region (up to 13 eV), the following 9028 1451 149 standard deviations were added to the contributions from 9028 1451 150 resonance parameters: 9028 1451 151 9028 1451 152 Total 12.6 % 9028 1451 153 Elastic scattering 50 % 9028 1451 154 Fission 90 % 9028 1451 155 Capture 10 % 9028 1451 156 9028 1451 157 9028 1451 158 MF=34 Covariances for Angular Distributions 9028 1451 159 MT=2 Elastic scattering 9028 1451 160 Covariances were given only to P1 components. 9028 1451 161 9028 1451 162 9028 1451 163 MF=35 Covariances for Energy Distributions 9028 1451 164 MT=18 Fission spectra 9028 1451 165 Estimated with CCONE and KALMAN codes. 9028 1451 166 9028 1451 167 9028 1451 168 ***************************************************************** 9028 1451 169 Calculation with CCONE code 9028 1451 170 ***************************************************************** 9028 1451 171 9028 1451 172 Models and parameters used in the CCONE/9/ calculation 9028 1451 173 1) Coupled channel optical model 9028 1451 174 Levels in the rotational band were included. Optical model 9028 1451 175 potential and coupled levels are shown in Table 1. 9028 1451 176 9028 1451 177 2) Two-component exciton model/14/ 9028 1451 178 * Global parametrization of Koning-Duijvestijn/15/ 9028 1451 179 was used. 9028 1451 180 * Gamma emission channel/16/ was added to simulate direct 9028 1451 181 and semi-direct capture reaction. 9028 1451 182 9028 1451 183 3) Hauser-Feshbach statistical model 9028 1451 184 * Moldauer width fluctuation correction/17/ was included. 9028 1451 185 * Neutron, gamma and fission decay channel were included. 9028 1451 186 * Transmission coefficients of neutrons were taken from 9028 1451 187 coupled channel calculation in Table 1. 9028 1451 188 * The level scheme of the target is shown in Table 2. 9028 1451 189 * Level density formula of constant temperature and Fermi-gas 9028 1451 190 model were used with shell energy correction and collective 9028 1451 191 enhancement factor. Parameters are shown in Table 3. 9028 1451 192 * Fission channel: 9028 1451 193 Double humped fission barriers were assumed. 9028 1451 194 Fission barrier penetrabilities were calculated with 9028 1451 195 Hill-Wheler formula/18/. Fission barrier parameters were 9028 1451 196 shown in Table 4. Transition state model was used and 9028 1451 197 continuum levels are assumed above the saddles. The level 9028 1451 198 density parameters for inner and outer saddles are shown in 9028 1451 199 Tables 5 and 6, respectively. 9028 1451 200 * Gamma-ray strength function of Kopecky et al/19/,/20/ 9028 1451 201 was used. The prameters are shown in Table 7. 9028 1451 202 9028 1451 203 9028 1451 204 ------------------------------------------------------------------9028 1451 205 Tables 9028 1451 206 ------------------------------------------------------------------9028 1451 207 9028 1451 208 Table 1. Coupled channel calculation 9028 1451 209 -------------------------------------------------- 9028 1451 210 * rigid rotor model was applied 9028 1451 211 * coupled levels = 0,1,2,4,7 (see Table 2) 9028 1451 212 * optical potential parameters /10/ 9028 1451 213 Volume: 9028 1451 214 V_0 = 49.97 MeV 9028 1451 215 lambda_HF = 0.01004 1/MeV 9028 1451 216 C_viso = 15.9 MeV 9028 1451 217 A_v = 12.04 MeV 9028 1451 218 B_v = 81.36 MeV 9028 1451 219 E_a = 385 MeV 9028 1451 220 r_v = 1.2568 fm 9028 1451 221 a_v = 0.633 fm 9028 1451 222 Surface: 9028 1451 223 W_0 = 17.2 MeV 9028 1451 224 B_s = 11.19 MeV 9028 1451 225 C_s = 0.01361 1/MeV 9028 1451 226 C_wiso = 23.5 MeV 9028 1451 227 r_s = 1.1803 fm 9028 1451 228 a_s = 0.601 fm 9028 1451 229 Spin-orbit: 9028 1451 230 V_so = 5.75 MeV 9028 1451 231 lambda_so = 0.005 1/MeV 9028 1451 232 W_so = -3.1 MeV 9028 1451 233 B_so = 160 MeV 9028 1451 234 r_so = 1.1214 fm 9028 1451 235 a_so = 0.59 fm 9028 1451 236 Coulomb: 9028 1451 237 C_coul = 1.3 9028 1451 238 r_c = 1.2452 fm 9028 1451 239 a_c = 0.545 fm 9028 1451 240 Deformation: 9028 1451 241 beta_2 = 0.213 9028 1451 242 beta_4 = 0.066 9028 1451 243 beta_6 = 0.0015 9028 1451 244 9028 1451 245 * Calculated strength function 9028 1451 246 S0= 1.07e-4 S1= 2.55e-4 R'= 9.88 fm (En=1 keV) 9028 1451 247 -------------------------------------------------- 9028 1451 248 9028 1451 249 Table 2. Level Scheme of Th-228 9028 1451 250 ------------------- 9028 1451 251 No. Ex(MeV) J PI 9028 1451 252 ------------------- 9028 1451 253 0 0.00000 0 + * 9028 1451 254 1 0.05776 2 + * 9028 1451 255 2 0.18682 4 + * 9028 1451 256 3 0.32800 1 - 9028 1451 257 4 0.37818 6 + * 9028 1451 258 5 0.39608 3 - 9028 1451 259 6 0.51919 5 - 9028 1451 260 7 0.62250 8 + * 9028 1451 261 8 0.69560 7 - 9028 1451 262 9 0.83182 0 + 9028 1451 263 10 0.87447 2 + 9028 1451 264 11 0.91180 10 + 9028 1451 265 12 0.92080 9 - 9028 1451 266 13 0.93858 0 + 9028 1451 267 14 0.94420 1 + 9028 1451 268 15 0.96837 3 - 9028 1451 269 16 0.96897 2 + 9028 1451 270 17 0.97950 2 + 9028 1451 271 18 1.01641 2 + 9028 1451 272 19 1.02253 3 + 9028 1451 273 20 1.05993 4 - 9028 1451 274 21 1.09102 4 + 9028 1451 275 22 1.12295 2 - 9028 1451 276 23 1.15347 2 + 9028 1451 277 24 1.16000 10 - 9028 1451 278 25 1.16837 3 - 9028 1451 279 26 1.17451 5 + 9028 1451 280 27 1.17539 2 + 9028 1451 281 28 1.18980 11 - 9028 1451 282 29 1.20054 3 + 9028 1451 283 ------------------- 9028 1451 284 *) Coupled levels in CC calculation 9028 1451 285 9028 1451 286 Table 3. Level density parameters 9028 1451 287 -------------------------------------------------------- 9028 1451 288 Nuclide a* Pair Eshell T E0 Ematch 9028 1451 289 1/MeV MeV MeV MeV MeV MeV 9028 1451 290 -------------------------------------------------------- 9028 1451 291 Th-229 17.7702 0.7930 3.2566 0.4327 -1.4313 3.7239 9028 1451 292 Th-228 17.7035 1.5894 3.0590 0.3964 -0.1539 3.9563 9028 1451 293 Th-227 17.6369 0.7965 3.1200 0.4219 -1.2457 3.5201 9028 1451 294 Th-226 17.5702 1.5965 2.8637 0.4068 -0.2170 4.0544 9028 1451 295 Th-225 17.5034 0.8000 2.7304 0.3997 -0.9049 3.1303 9028 1451 296 -------------------------------------------------------- 9028 1451 297 9028 1451 298 Table 4. Fission barrier parameters 9028 1451 299 ---------------------------------------- 9028 1451 300 Nuclide V_A hw_A V_B hw_B 9028 1451 301 MeV MeV MeV MeV 9028 1451 302 ---------------------------------------- 9028 1451 303 Th-229 5.500 0.800 6.000 0.520 9028 1451 304 Th-228 3.900 1.040 6.400 0.600 9028 1451 305 Th-227 4.100 0.800 6.400 0.520 9028 1451 306 Th-226 3.900 1.040 8.200 0.600 9028 1451 307 Th-225 4.200 0.800 8.000 0.520 9028 1451 308 ---------------------------------------- 9028 1451 309 9028 1451 310 Table 5. Level density above inner saddle 9028 1451 311 -------------------------------------------------------- 9028 1451 312 Nuclide a* Pair Eshell T E0 Ematch 9028 1451 313 1/MeV MeV MeV MeV MeV MeV 9028 1451 314 -------------------------------------------------------- 9028 1451 315 Th-229 19.9026 0.9251 2.6000 0.3339 -1.4862 2.9251 9028 1451 316 Th-228 19.8280 1.8543 2.6000 0.3346 -0.5570 3.8543 9028 1451 317 Th-227 19.7533 0.9292 2.6000 0.3352 -1.4822 2.9292 9028 1451 318 Th-226 19.6786 1.8625 2.6000 0.3359 -0.5488 3.8625 9028 1451 319 Th-225 19.6038 0.9333 2.6000 0.3366 -1.4780 2.9333 9028 1451 320 -------------------------------------------------------- 9028 1451 321 9028 1451 322 Table 6. Level density above outer saddle 9028 1451 323 -------------------------------------------------------- 9028 1451 324 Nuclide a* Pair Eshell T E0 Ematch 9028 1451 325 1/MeV MeV MeV MeV MeV MeV 9028 1451 326 -------------------------------------------------------- 9028 1451 327 Th-229 19.9026 0.9251 -0.2600 0.3799 -0.7708 2.9251 9028 1451 328 Th-228 19.8280 1.8543 -0.3000 0.3812 0.1590 3.8543 9028 1451 329 Th-227 19.7533 0.9292 -0.3400 0.3826 -0.7655 2.9292 9028 1451 330 Th-226 19.6786 1.8625 -0.3800 0.3840 0.1685 3.8625 9028 1451 331 Th-225 19.6038 0.9333 -0.4200 0.3854 -0.7601 2.9333 9028 1451 332 -------------------------------------------------------- 9028 1451 333 9028 1451 334 Table 7. Gamma-ray strength function for Th-229 9028 1451 335 -------------------------------------------------------- 9028 1451 336 K0 = 1.502 E0 = 4.500 (MeV) 9028 1451 337 * E1: ER = 11.03 (MeV) EG = 2.71 (MeV) SIG = 302.00 (mb) 9028 1451 338 ER = 13.87 (MeV) EG = 4.77 (MeV) SIG = 449.00 (mb) 9028 1451 339 * M1: ER = 6.70 (MeV) EG = 4.00 (MeV) SIG = 2.81 (mb) 9028 1451 340 * E2: ER = 10.30 (MeV) EG = 3.36 (MeV) SIG = 6.26 (mb) 9028 1451 341 -------------------------------------------------------- 9028 1451 342 9028 1451 343 9028 1451 344 References 9028 1451 345 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9028 1451 346 2) R.J.Tutle: INDC(NDS)-107/G+SPECIAL, P.29 (1979), 9028 1451 347 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 9028 1451 348 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 9028 1451 349 5) T.Ohsawa: J. Nucl. Radiochem. Sci., 9, 19 (2008). 9028 1451 350 6) O.D.Simpson et al.: Nucl. Sci. Eng., 29, 423 (1967). 9028 1451 351 7) S.F.Mughabghab: "Atlas of Neutron Resonances," Elsevier 9028 1451 352 (2006). 9028 1451 353 8) Y.Kikuchi, et al.: JAERI-Data/Code 99-025 (1999) in Japanese. 9028 1451 354 9) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9028 1451 355 10) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9028 1451 356 11) G.D.James et al.:Nucl. Phys. A419, 497 (1984) 9028 1451 357 12) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9028 1451 358 13) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9028 1451 359 Japanese. 9028 1451 360 14) C.Kalbach: Phys. Rev. C33, 818 (1986). 9028 1451 361 15) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9028 1451 362 16) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9028 1451 363 17) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9028 1451 364 18) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9028 1451 365 19) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9028 1451 366 20) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9028 1451 367 9028 1451 368 1 451 380 19028 1451 369 2 151 4 19028 1451 370 3 4 34 19028 1451 371 3 16 12 19028 1451 372 3 17 9 19028 1451 373 3 18 134 19028 1451 374 3 102 348 19028 1451 375 8 4 2 19028 1451 376 8 16 2 19028 1451 377 8 17 2 19028 1451 378 8 18 2 19028 1451 379 8 102 2 19028 1451 380 9028 1 099999 9028 0 0 0 9.022800+4 2.260700+2 0 0 1 09028 2151 1 9.022800+4 1.000000+0 0 0 1 09028 2151 2 1.000000-5 1.300000+1 0 0 0 09028 2151 3 0.000000+0 1.092500+0 0 0 0 09028 2151 4 9028 2 099999 9028 0 0 0 9.022800+4 2.260700+2 0 0 0 09028 3 4 1 0.000000+0-5.775900+4 0 0 1 939028 3 4 2 93 2 9028 3 4 3 5.801450+4 0.000000+0 7.000000+4 1.308860-1 1.000000+5 4.045180-19028 3 4 4 1.109750+5 4.659160-1 1.200000+5 5.164172-1 1.400000+5 6.069206-19028 3 4 5 1.700000+5 7.276657-1 1.876490+5 7.959373-1 2.000000+5 8.457348-19028 3 4 6 2.500000+5 9.577956-1 3.000000+5 1.079513+0 3.294540+5 1.106106+09028 3 4 7 3.798520+5 1.352265+0 3.978300+5 1.403661+0 4.000000+5 1.410639+09028 3 4 8 5.000000+5 1.698503+0 5.214890+5 1.725535+0 6.000000+5 1.820577+09028 3 4 9 6.252540+5 1.852314+0 6.986770+5 1.947090+0 7.000000+5 1.948808+09028 3 4 10 8.000000+5 2.000845+0 8.355020+5 2.016513+0 8.783410+5 2.050027+09028 3 4 11 9.000000+5 2.075637+0 9.158330+5 2.091669+0 9.248730+5 2.100386+09028 3 4 12 9.427320+5 2.116614+0 9.483730+5 2.124584+0 9.726520+5 2.163082+09028 3 4 13 9.732540+5 2.164521+0 9.838320+5 2.186417+0 1.000000+6 2.221379+09028 3 4 14 1.020900+6 2.255598+0 1.027050+6 2.267740+0 1.064620+6 2.329875+09028 3 4 15 1.095840+6 2.371865+0 1.100000+6 2.376792+0 1.127920+6 2.406805+09028 3 4 16 1.158570+6 2.439823+0 1.165130+6 2.448560+0 1.173540+6 2.457530+09028 3 4 17 1.179700+6 2.464857+0 1.180590+6 2.465830+0 1.195060+6 2.483405+09028 3 4 18 1.200000+6 2.488714+0 1.205850+6 2.494982+0 1.300000+6 2.575302+09028 3 4 19 1.400000+6 2.632643+0 1.500000+6 2.684056+0 1.600000+6 2.728275+09028 3 4 20 1.700000+6 2.767418+0 1.800000+6 2.801453+0 1.900000+6 2.830307+09028 3 4 21 2.000000+6 2.856086+0 2.300000+6 2.903920+0 2.500000+6 2.917315+09028 3 4 22 2.700000+6 2.922118+0 3.000000+6 2.916705+0 3.500000+6 2.888313+09028 3 4 23 4.000000+6 2.858872+0 4.500000+6 2.830388+0 5.000000+6 2.833583+09028 3 4 24 5.500000+6 2.817866+0 6.000000+6 2.824799+0 6.500000+6 2.806493+09028 3 4 25 7.000000+6 2.714694+0 7.500000+6 2.503880+0 8.000000+6 2.140897+09028 3 4 26 8.500000+6 1.726919+0 9.000000+6 1.390616+0 9.500000+6 1.137994+09028 3 4 27 1.000000+7 9.595475-1 1.050000+7 8.400893-1 1.100000+7 7.489900-19028 3 4 28 1.150000+7 6.791671-1 1.200000+7 6.241530-1 1.250000+7 5.860570-19028 3 4 29 1.300000+7 5.490679-1 1.350000+7 5.224305-1 1.400000+7 4.984139-19028 3 4 30 1.450000+7 4.812326-1 1.500000+7 4.613555-1 1.550000+7 4.432741-19028 3 4 31 1.600000+7 4.294363-1 1.650000+7 4.131002-1 1.700000+7 4.006005-19028 3 4 32 1.750000+7 3.892682-1 1.800000+7 3.778529-1 1.850000+7 3.672741-19028 3 4 33 1.900000+7 3.568000-1 1.950000+7 3.470946-1 2.000000+7 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