JENDL-5 (Neutron sublibrary (activation cs)) Th-234 0 0 0 0 9.023400+4 2.320330+2 0 0 6 19046 1451 1 0.000000+0 1.000000+0 0 0 0 69046 1451 2 1.000000+0 2.000000+7 0 0 10 59046 1451 3 2.936000+2 0.000000+0 4 0 310 149046 1451 4 90-Th-234 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9046 1451 5 DIST-DEC21 20100303 9046 1451 6 ----JENDL-5 MATERIAL 9046 9046 1451 7 -----INCIDENT NEUTRON DATA 9046 1451 8 ------ENDF-6 FORMAT 9046 1451 9 9046 1451 10 History 9046 1451 11 07-06 Theoretical calculation was performed with CCONE code. 9046 1451 12 07-07 Data were compiled as JENDL/AC-2008/1/. 9046 1451 13 10-02 Data of prompt gamma rays due to fission were given. 9046 1451 14 10-03 Covariance data were given. 9046 1451 15 21-11 revised by O.Iwamoto 9046 1451 16 (MF3/MT19-21,38) deleted 9046 1451 17 (MF8/MT4,16-18,37,102) added 9046 1451 18 9046 1451 19 9046 1451 20 MF=1 General information 9046 1451 21 MT=452 Number of Neutrons per fission 9046 1451 22 Sum of MT's=455 and 456. 9046 1451 23 9046 1451 24 MT=455 Delayed neutron data 9046 1451 25 (Same as JENDL-3.3) 9046 1451 26 Average values of systematics of Tuttle/2/, Benedetti et 9046 1451 27 al./3/ and Waldo et al./4/ 9046 1451 28 9046 1451 29 MT=456 Number of prompt neutrons per fission 9046 1451 30 (Same as JENDL-3.3) 9046 1451 31 Based on the semi-empirical formula of Howerton/5/. 9046 1451 32 9046 1451 33 9046 1451 34 MF= 2 Resonance parameters 9046 1451 35 MT=151 9046 1451 36 No resonance parameters are given. 9046 1451 37 9046 1451 38 9046 1451 39 Thermal cross sections and resonance integrals (at 300K) 9046 1451 40 ------------------------------------------------------- 9046 1451 41 0.0253 eV reson. integ.(*) 9046 1451 42 (barns) (barns) 9046 1451 43 ------------------------------------------------------- 9046 1451 44 total 13.75 9046 1451 45 elastic 11.93 9046 1451 46 fission 0.005 0.196 9046 1451 47 capture 1.80 31.4 9046 1451 48 ------------------------------------------------------- 9046 1451 49 (*) In the energy range from 0.5 eV to 10 MeV. 9046 1451 50 9046 1451 51 9046 1451 52 MF= 3 Neutron cross sections 9046 1451 53 Below 20 eV: 9046 1451 54 Elastic scattering cross section is 11.9 b calculated from 9046 1451 55 scattering radius/6/. 9046 1451 56 Fission cross section is in the 1/v shape, and 0.005 b at 9046 1451 57 0.0253 eV/7/. 9046 1451 58 Capture cross section is also in the 1/v shape, and 1.8 b 9046 1451 59 at 0.0253 eV/7,8/. 9046 1451 60 9046 1451 61 Above 20 eV: 9046 1451 62 Cross sections were calculated with CCONE code. 9046 1451 63 9046 1451 64 MT= 1 Total cross section 9046 1451 65 The cross section was calculated with CC OMP of Soukhovitskii 9046 1451 66 et al./9/. 9046 1451 67 9046 1451 68 9046 1451 69 MF= 4 Angular distributions of secondary neutrons 9046 1451 70 MT=2 Elastic scattering 9046 1451 71 Calculated with CCONE code/6/. 9046 1451 72 9046 1451 73 MT=18 Fission 9046 1451 74 Isotropic distributions in the laboratory system were assumed.9046 1451 75 9046 1451 76 9046 1451 77 MF= 5 Energy distributions of secondary neutrons 9046 1451 78 MT=18 Prompt neutrons 9046 1451 79 Calculated with CCONE code/6/. 9046 1451 80 9046 1451 81 9046 1451 82 MF= 6 Energy-angle distributions 9046 1451 83 Calculated with CCONE code/6/. 9046 1451 84 Distributions from fission (MT=18) are not included. 9046 1451 85 9046 1451 86 9046 1451 87 MF=12 Photon production multiplicities 9046 1451 88 MT=18 Fission 9046 1451 89 Calculated from the total energy released by the prompt 9046 1451 90 gamma-rays due to fission which was estimated from its 9046 1451 91 systematics, and the average energy of gamma-rays. 9046 1451 92 9046 1451 93 9046 1451 94 MF=14 Photon angular distributions 9046 1451 95 MT=18 Fission 9046 1451 96 Isotoropic distributions were assumed. 9046 1451 97 9046 1451 98 9046 1451 99 MF=15 Continuous photon energy spectra 9046 1451 100 MT=18 Fission 9046 1451 101 Experimental data measured by Verbinski et al./10/ for 9046 1451 102 U-235 thermal fission were adopted. 9046 1451 103 9046 1451 104 9046 1451 105 MF=31 Covariances of average number of neutrons per fission 9046 1451 106 MT=452 Number of neutrons per fission 9046 1451 107 Sum of covariances for MT=455 and MT=456. 9046 1451 108 9046 1451 109 MT=455 9046 1451 110 Error of 15% was assumed. 9046 1451 111 9046 1451 112 MT=456 9046 1451 113 Covariance was obtained by fitting a linear function to the 9046 1451 114 at 0.0 and 5.0 MeV with an uncertainty of 5%. 9046 1451 115 9046 1451 116 9046 1451 117 MF=33 Covariances of neutron cross sections 9046 1451 118 Covariances were given to all the cross sections by using 9046 1451 119 KALMAN code/11/ and the covariances of model parameters 9046 1451 120 used in the cross-section calculations. 9046 1451 121 9046 1451 122 For the following cross sections, standard deviations in the 9046 1451 123 energy region below 20 eV were assumed as follows: 9046 1451 124 9046 1451 125 Total 44 % 9046 1451 126 Elastic scattering 50 % 9046 1451 127 Fission 50 % 9046 1451 128 Capture 50 % 9046 1451 129 9046 1451 130 9046 1451 131 MF=34 Covariances for Angular Distributions 9046 1451 132 MT=2 Elastic scattering 9046 1451 133 Covariances were given only to P1 components. 9046 1451 134 9046 1451 135 9046 1451 136 MF=35 Covariances for Energy Distributions 9046 1451 137 MT=18 Fission spectra 9046 1451 138 Estimated with CCONE and KALMAN codes. 9046 1451 139 9046 1451 140 9046 1451 141 ***************************************************************** 9046 1451 142 Calculation with CCONE code 9046 1451 143 ***************************************************************** 9046 1451 144 9046 1451 145 Models and parameters used in the CCONE/6/ calculation 9046 1451 146 1) Coupled channel optical model 9046 1451 147 Levels in the rotational band were included. Optical model 9046 1451 148 potential and coupled levels are shown in Table 1. 9046 1451 149 9046 1451 150 2) Two-component exciton model/12/ 9046 1451 151 * Global parametrization of Koning-Duijvestijn/13/ 9046 1451 152 was used. 9046 1451 153 * Gamma emission channel/14/ was added to simulate direct 9046 1451 154 and semi-direct capture reaction. 9046 1451 155 9046 1451 156 3) Hauser-Feshbach statistical model 9046 1451 157 * Moldauer width fluctuation correction/15/ was included. 9046 1451 158 * Neutron, gamma and fission decay channel were included. 9046 1451 159 * Transmission coefficients of neutrons were taken from 9046 1451 160 coupled channel calculation in Table 1. 9046 1451 161 * The level scheme of the target is shown in Table 2. 9046 1451 162 * Level density formula of constant temperature and Fermi-gas 9046 1451 163 model were used with shell energy correction and collective 9046 1451 164 enhancement factor. Parameters are shown in Table 3. 9046 1451 165 * Fission channel: 9046 1451 166 Double humped fission barriers were assumed. 9046 1451 167 Fission barrier penetrabilities were calculated with 9046 1451 168 Hill-Wheler formula/16/. Fission barrier parameters were 9046 1451 169 shown in Table 4. Transition state model was used and 9046 1451 170 continuum levels are assumed above the saddles. The level 9046 1451 171 density parameters for inner and outer saddles are shown in 9046 1451 172 Tables 5 and 6, respectively. 9046 1451 173 * Gamma-ray strength function of Kopecky et al/17/,/18/ 9046 1451 174 was used. The prameters are shown in Table 7. 9046 1451 175 9046 1451 176 9046 1451 177 ------------------------------------------------------------------9046 1451 178 Tables 9046 1451 179 ------------------------------------------------------------------9046 1451 180 9046 1451 181 Table 1. Coupled channel calculation 9046 1451 182 -------------------------------------------------- 9046 1451 183 * rigid rotor model was applied 9046 1451 184 * coupled levels = 0,1,2,3,4 (see Table 2) 9046 1451 185 * optical potential parameters /9/ 9046 1451 186 Volume: 9046 1451 187 V_0 = 49.97 MeV 9046 1451 188 lambda_HF = 0.01004 1/MeV 9046 1451 189 C_viso = 15.9 MeV 9046 1451 190 A_v = 12.04 MeV 9046 1451 191 B_v = 81.36 MeV 9046 1451 192 E_a = 385 MeV 9046 1451 193 r_v = 1.2568 fm 9046 1451 194 a_v = 0.633 fm 9046 1451 195 Surface: 9046 1451 196 W_0 = 17.2 MeV 9046 1451 197 B_s = 11.19 MeV 9046 1451 198 C_s = 0.01361 1/MeV 9046 1451 199 C_wiso = 23.5 MeV 9046 1451 200 r_s = 1.1803 fm 9046 1451 201 a_s = 0.601 fm 9046 1451 202 Spin-orbit: 9046 1451 203 V_so = 5.75 MeV 9046 1451 204 lambda_so = 0.005 1/MeV 9046 1451 205 W_so = -3.1 MeV 9046 1451 206 B_so = 160 MeV 9046 1451 207 r_so = 1.1214 fm 9046 1451 208 a_so = 0.59 fm 9046 1451 209 Coulomb: 9046 1451 210 C_coul = 1.3 9046 1451 211 r_c = 1.2452 fm 9046 1451 212 a_c = 0.545 fm 9046 1451 213 Deformation: 9046 1451 214 beta_2 = 0.213 9046 1451 215 beta_4 = 0.066 9046 1451 216 beta_6 = 0.0015 9046 1451 217 9046 1451 218 * Calculated strength function 9046 1451 219 S0= 0.79e-4 S1= 2.14e-4 R'= 9.69 fm (En=1 keV) 9046 1451 220 -------------------------------------------------- 9046 1451 221 9046 1451 222 Table 2. Level Scheme of Th-234 9046 1451 223 ------------------- 9046 1451 224 No. Ex(MeV) J PI 9046 1451 225 ------------------- 9046 1451 226 0 0.00000 0 + * 9046 1451 227 1 0.04955 2 + * 9046 1451 228 2 0.16300 4 + * 9046 1451 229 3 0.33650 6 + * 9046 1451 230 4 0.56480 8 + * 9046 1451 231 ------------------- 9046 1451 232 *) Coupled levels in CC calculation 9046 1451 233 9046 1451 234 Table 3. Level density parameters 9046 1451 235 -------------------------------------------------------- 9046 1451 236 Nuclide a* Pair Eshell T E0 Ematch 9046 1451 237 1/MeV MeV MeV MeV MeV MeV 9046 1451 238 -------------------------------------------------------- 9046 1451 239 Th-235 18.1694 0.7828 3.8956 0.2682 0.1087 1.7828 9046 1451 240 Th-234 18.1029 1.5689 3.6260 0.3733 -0.0455 3.7635 9046 1451 241 Th-233 18.8481 0.7861 3.5545 0.3805 -1.0048 3.1955 9046 1451 242 Th-232 18.7786 1.5757 3.3953 0.3835 -0.2200 3.9949 9046 1451 243 Th-231 18.7090 0.7895 3.3191 0.3770 -0.9082 3.0943 9046 1451 244 -------------------------------------------------------- 9046 1451 245 9046 1451 246 Table 4. Fission barrier parameters 9046 1451 247 ---------------------------------------- 9046 1451 248 Nuclide V_A hw_A V_B hw_B 9046 1451 249 MeV MeV MeV MeV 9046 1451 250 ---------------------------------------- 9046 1451 251 Th-235 5.820 1.000 6.150 0.530 9046 1451 252 Th-234 5.800 1.040 5.950 0.500 9046 1451 253 Th-233 5.820 1.000 6.150 0.530 9046 1451 254 Th-232 5.800 1.040 5.950 0.500 9046 1451 255 Th-231 6.000 0.800 6.000 0.600 9046 1451 256 ---------------------------------------- 9046 1451 257 9046 1451 258 Table 5. Level density above inner saddle 9046 1451 259 -------------------------------------------------------- 9046 1451 260 Nuclide a* Pair Eshell T E0 Ematch 9046 1451 261 1/MeV MeV MeV MeV MeV MeV 9046 1451 262 -------------------------------------------------------- 9046 1451 263 Th-235 20.3497 0.9133 2.6000 0.3299 -1.4981 2.9133 9046 1451 264 Th-234 20.2753 1.8304 2.6000 0.3306 -0.5810 3.8304 9046 1451 265 Th-233 20.2008 0.9172 2.6000 0.3312 -1.4942 2.9172 9046 1451 266 Th-232 20.1263 1.8383 2.6000 0.3319 -0.5731 3.8383 9046 1451 267 Th-231 19.6937 0.9211 2.6000 0.3507 -1.7165 3.1211 9046 1451 268 -------------------------------------------------------- 9046 1451 269 9046 1451 270 Table 6. Level density above outer saddle 9046 1451 271 -------------------------------------------------------- 9046 1451 272 Nuclide a* Pair Eshell T E0 Ematch 9046 1451 273 1/MeV MeV MeV MeV MeV MeV 9046 1451 274 -------------------------------------------------------- 9046 1451 275 Th-235 20.3497 0.9133 -0.0200 0.3720 -0.7864 2.9133 9046 1451 276 Th-234 20.2753 1.8304 -0.0600 0.3733 0.1314 3.8304 9046 1451 277 Th-233 20.7419 0.9172 -0.1000 0.3835 -0.9412 3.1172 9046 1451 278 Th-232 20.5756 1.8383 -0.1400 0.3595 0.2690 3.6883 9046 1451 279 Th-231 19.6937 0.9211 -0.1800 0.3963 -0.9457 3.1211 9046 1451 280 -------------------------------------------------------- 9046 1451 281 9046 1451 282 Table 7. Gamma-ray strength function for Th-235 9046 1451 283 -------------------------------------------------------- 9046 1451 284 K0 = 1.501 E0 = 4.500 (MeV) 9046 1451 285 * E1: ER = 11.03 (MeV) EG = 2.71 (MeV) SIG = 302.00 (mb) 9046 1451 286 ER = 13.87 (MeV) EG = 4.77 (MeV) SIG = 449.00 (mb) 9046 1451 287 * M1: ER = 6.64 (MeV) EG = 4.00 (MeV) SIG = 2.77 (mb) 9046 1451 288 * E2: ER = 10.21 (MeV) EG = 3.29 (MeV) SIG = 6.24 (mb) 9046 1451 289 -------------------------------------------------------- 9046 1451 290 9046 1451 291 9046 1451 292 References 9046 1451 293 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9046 1451 294 2) R.J.Tuttle: INDC(NDS)-107/G+SPECIAL, P.29 (1979), 9046 1451 295 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 9046 1451 296 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 9046 1451 297 5) R.J.Howerton: Nucl. Sci. Eng. 62, 438 (1977). 9046 1451 298 6) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9046 1451 299 7) S.F.Mughabghab: "Atlas of Neutron Resonances," Elsevier 9046 1451 300 (2006). 9046 1451 301 8) B.G.Harvey, B.I.Parsons: Phys. Rev., 80, 1098 (1950). 9046 1451 302 9) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9046 1451 303 10) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9046 1451 304 11) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9046 1451 305 Japanese. 9046 1451 306 12) C.Kalbach: Phys. Rev. C33, 818 (1986). 9046 1451 307 13) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9046 1451 308 14) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9046 1451 309 15) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9046 1451 310 16) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9046 1451 311 17) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9046 1451 312 18) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9046 1451 313 9046 1451 314 1 451 328 19046 1451 315 2 151 4 19046 1451 316 3 4 26 19046 1451 317 3 16 13 19046 1451 318 3 17 10 19046 1451 319 3 18 218 19046 1451 320 3 37 5 19046 1451 321 3 102 183 19046 1451 322 8 4 2 19046 1451 323 8 16 2 19046 1451 324 8 17 2 19046 1451 325 8 18 2 19046 1451 326 8 37 2 19046 1451 327 8 102 2 19046 1451 328 9046 1 099999 9046 0 0 0 9.023400+4 2.320330+2 0 0 1 09046 2151 1 9.023400+4 1.000000+0 0 0 1 09046 2151 2 1.000000-5 2.000000+1 0 0 0 09046 2151 3 0.000000+0 9.730200-1 0 0 0 09046 2151 4 9046 2 099999 9046 0 0 0 9.023400+4 2.320330+2 0 0 0 09046 3 4 1 0.000000+0-4.955000+4 0 0 1 699046 3 4 2 69 2 9046 3 4 3 4.976350+4 0.000000+0 5.000000+4 1.167850-2 7.000000+4 2.449130-19046 3 4 4 1.000000+5 4.761350-1 1.109500+5 5.266145-1 1.200000+5 5.683422-19046 3 4 5 1.400000+5 6.495135-1 1.637020+5 7.418813-1 1.700000+5 7.665860-19046 3 4 6 2.000000+5 8.901862-1 2.500000+5 1.012855+0 3.000000+5 1.150052+09046 3 4 7 3.379500+5 1.198788+0 4.000000+5 1.294435+0 5.000000+5 1.506203+09046 3 4 8 5.672340+5 1.587250+0 6.000000+5 1.629096+0 7.000000+5 1.803686+09046 3 4 9 8.000000+5 1.960753+0 9.000000+5 2.143165+0 1.000000+6 2.346552+09046 3 4 10 1.100000+6 2.527396+0 1.200000+6 2.696984+0 1.300000+6 2.854437+09046 3 4 11 1.400000+6 2.995121+0 1.500000+6 3.121648+0 1.600000+6 3.229369+09046 3 4 12 1.700000+6 3.318615+0 1.800000+6 3.390322+0 1.900000+6 3.444235+09046 3 4 13 2.000000+6 3.488448+0 2.300000+6 3.560335+0 2.500000+6 3.575061+09046 3 4 14 2.700000+6 3.576024+0 3.000000+6 3.559625+0 3.500000+6 3.516031+09046 3 4 15 4.000000+6 3.461448+0 4.500000+6 3.390375+0 5.000000+6 3.339653+09046 3 4 16 5.500000+6 3.275772+0 6.000000+6 3.232565+0 6.500000+6 2.950296+09046 3 4 17 7.000000+6 2.269022+0 7.500000+6 1.668873+0 8.000000+6 1.273838+09046 3 4 18 8.500000+6 1.018280+0 9.000000+6 8.607463-1 9.500000+6 7.574016-19046 3 4 19 1.000000+7 6.878860-1 1.050000+7 6.373503-1 1.100000+7 5.975260-19046 3 4 20 1.150000+7 5.667961-1 1.200000+7 5.385369-1 1.250000+7 5.149804-19046 3 4 21 1.300000+7 4.930069-1 1.350000+7 4.728010-1 1.400000+7 4.546056-19046 3 4 22 1.450000+7 4.378280-1 1.500000+7 4.200201-1 1.550000+7 4.059787-19046 3 4 23 1.600000+7 3.923053-1 1.650000+7 3.781161-1 1.700000+7 3.651094-19046 3 4 24 1.750000+7 3.536806-1 1.800000+7 3.425408-1 1.850000+7 3.325739-19046 3 4 25 1.900000+7 3.232940-1 1.950000+7 3.139240-1 2.000000+7 3.058300-19046 3 4 26 9046 3 099999 9.023400+4 2.320330+2 0 0 0 09046 3 16 1 -6.190270+6-6.190270+6 0 0 1 299046 3 16 2 29 2 9046 3 16 3 6.216950+6 0.000000+0 6.500000+6 1.019700-1 7.000000+6 7.288410-19046 3 16 4 7.500000+6 1.336750+0 8.000000+6 1.765180+0 8.500000+6 2.031030+09046 3 16 5 9.000000+6 2.199730+0 9.500000+6 2.294910+0 1.000000+7 2.355860+09046 3 16 6 1.050000+7 2.389570+0 1.100000+7 2.413300+0 1.150000+7 2.424080+09046 3 16 7 1.200000+7 2.386820+0 1.250000+7 2.240080+0 1.300000+7 2.023390+09046 3 16 8 1.350000+7 1.763290+0 1.400000+7 1.505830+0 1.450000+7 1.269470+09046 3 16 9 1.500000+7 1.067560+0 1.550000+7 9.028240-1 1.600000+7 7.822640-19046 3 16 10 1.650000+7 6.759400-1 1.700000+7 6.003680-1 1.750000+7 5.423230-19046 3 16 11 1.800000+7 4.939460-1 1.850000+7 4.573830-1 1.900000+7 4.319720-19046 3 16 12 1.950000+7 4.064840-1 2.000000+7 3.891410-1 9046 3 16 13 9046 3 099999 9.023400+4 2.320330+2 0 0 0 09046 3 17 1 -1.097670+7-1.097670+7 0 0 1 199046 3 17 2 19 2 9046 3 17 3 1.102400+7 0.000000+0 1.150000+7 2.238920-3 1.200000+7 5.124600-29046 3 17 4 1.250000+7 2.064720-1 1.300000+7 4.280540-1 1.350000+7 6.891250-19046 3 17 5 1.400000+7 9.366500-1 1.450000+7 1.161200+0 1.500000+7 1.352350+09046 3 17 6 1.550000+7 1.506420+0 1.600000+7 1.613330+0 1.650000+7 1.717960+09046 3 17 7 1.700000+7 1.787550+0 1.750000+7 1.842180+0 1.800000+7 1.887160+09046 3 17 8 1.850000+7 1.918100+0 1.900000+7 1.925380+0 1.950000+7 1.916270+09046 3 17 9 2.000000+7 1.869250+0 9046 3 17 10 9046 3 099999 9.023400+4 2.320330+2 0 0 0 09046 3 18 1 1.895000+8 1.895000+8 0 0 1 6439046 3 18 2 643 2 9046 3 18 3 1.000000-5 2.504777-1 1.103037-5 2.384932-1 1.216691-5 2.270822-19046 3 18 4 1.342055-5 2.162173-1 1.480336-5 2.058724-1 1.632865-5 1.960225-19046 3 18 5 1.801111-5 1.866440-1 1.986691-5 1.777143-1 2.191394-5 1.692120-19046 3 18 6 2.417189-5 1.611166-1 2.666248-5 1.534086-1 2.940971-5 1.460695-19046 3 18 7 3.243999-5 1.390817-1 3.578251-5 1.324283-1 3.946943-5 1.260934-19046 3 18 8 4.353624-5 1.200616-1 4.802208-5 1.143186-1 5.297013-5 1.088504-19046 3 18 9 5.842801-5 1.036439-1 6.444825-5 9.868669-2 7.108881-5 9.396671-29046 3 18 10 7.841358-5 8.947265-2 8.649308-5 8.519368-2 9.540506-5 8.111953-29046 3 18 11 1.052353-4 7.724037-2 1.160784-4 7.354689-2 1.280388-4 7.003018-29046 3 18 12 1.412315-4 6.668177-2 1.557836-4 6.349362-2 1.718351-4 6.045804-29046 3 18 13 1.895404-4 5.756772-2 2.090701-4 5.481571-2 2.306120-4 5.219537-29046 3 18 14 2.543736-4 4.970040-2 2.805835-4 4.732479-2 3.094939-4 4.506282-29046 3 18 15 3.413832-4 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