JENDL-5 (Neutron sublibrary (activation cs)) Pu-246 0 0 0 0 9.424600+4 2.439560+2 0 0 6 19458 1451 1 0.000000+0 1.000000+0 0 0 0 69458 1451 2 1.000000+0 2.000000+7 0 0 10 59458 1451 3 2.936000+2 0.000000+0 4 0 310 149458 1451 4 94-Pu-246 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9458 1451 5 DIST-DEC21 20100303 9458 1451 6 ----JENDL-5 MATERIAL 9458 9458 1451 7 -----INCIDENT NEUTRON DATA 9458 1451 8 ------ENDF-6 FORMAT 9458 1451 9 9458 1451 10 History 9458 1451 11 07-08 Theoretical calculation was performed with CCONE code. 9458 1451 12 Data were compiled as JENDL/AC-2008/1/. 9458 1451 13 10-02 Data of prompt gamma rays due to fission were given. 9458 1451 14 10-03 Covariance data were given. 9458 1451 15 21-11 revised by O.Iwamoto 9458 1451 16 (MF3/MT19-21,38) deleted 9458 1451 17 (MF8/MT4,16-18,37,102) added 9458 1451 18 9458 1451 19 9458 1451 20 MF=1 General information 9458 1451 21 MT=452 Number of Neutrons per fission 9458 1451 22 Sum of MT's=455 and 456. 9458 1451 23 9458 1451 24 MT=455 Delayed neutron data 9458 1451 25 (Same as JENDL-3.3) 9458 1451 26 Tuttle's systematics/2/ was adopted. 9458 1451 27 9458 1451 28 MT=456 Number of prompt neutrons per fission 9458 1451 29 Obtained from Howerton's sytematics/3/. 9458 1451 30 9458 1451 31 9458 1451 32 MF= 2 Resonance parameters 9458 1451 33 MT=151 9458 1451 34 No resonance parameters are given. 9458 1451 35 9458 1451 36 9458 1451 37 Thermal cross sections and resonance integrals (at 300K) 9458 1451 38 ------------------------------------------------------- 9458 1451 39 0.0253 eV reson. integ.(*) 9458 1451 40 (barns) (barns) 9458 1451 41 ------------------------------------------------------- 9458 1451 42 total 91.067 9458 1451 43 elastic 10.923 9458 1451 44 fission 0.0032 2.03 9458 1451 45 capture 80.032 68.1 9458 1451 46 ------------------------------------------------------- 9458 1451 47 (*) In the energy range from 0.5 eV to 10 MeV. 9458 1451 48 9458 1451 49 9458 1451 50 MF= 3 Neutron cross sections 9458 1451 51 Below 18.0 eV: 9458 1451 52 Elastic scattering cross section is 10.9 b calculated from 9458 1451 53 scattering radius of 9.32fm/4/. 9458 1451 54 Fission cross section is in the 1/v shape, and 0.12 mb at 18 9458 1451 55 eV was assumed. 9458 1451 56 Capture cross section is in the 1/v shape, and 3 b at 18 eV 9458 1451 57 which is about 1/10 of CCONE calculation. 9458 1451 58 9458 1451 59 Above 18.0 eV: 9458 1451 60 Cross sections were calculated with CCONE code/4/, except 9458 1451 61 for the fission cross section below 100 keV which was assumed 9458 1451 62 to be 0.12 mb calculated at 100 keV with CCONE code. 9458 1451 63 9458 1451 64 MT= 1 Total cross section 9458 1451 65 The cross section was calculated with CC OMP of Soukhovitskii 9458 1451 66 et al./5/ 9458 1451 67 9458 1451 68 9458 1451 69 MF= 4 Angular distributions of secondary neutrons 9458 1451 70 MT=2 Elastic scattering 9458 1451 71 Calculated with CCONE code. 9458 1451 72 9458 1451 73 MT=18 Fission 9458 1451 74 Isotropic distributions in the laboratory system were assumed.9458 1451 75 9458 1451 76 9458 1451 77 MF= 5 Energy distributions of secondary neutrons 9458 1451 78 MT=18 Fission spectra 9458 1451 79 Calculated with CCONE code. 9458 1451 80 9458 1451 81 9458 1451 82 MF= 6 Energy-angle distributions 9458 1451 83 Calculated with CCONE code. 9458 1451 84 Distributions from fission (MT=18) are not included. 9458 1451 85 9458 1451 86 9458 1451 87 MF=12 Photon production multiplicities 9458 1451 88 MT=18 Fission 9458 1451 89 Calculated from the total energy released by the prompt 9458 1451 90 gamma-rays due to fission which was estimated from its 9458 1451 91 systematics, and the average energy of gamma-rays. 9458 1451 92 9458 1451 93 9458 1451 94 MF=14 Photon angular distributions 9458 1451 95 MT=18 Fission 9458 1451 96 Isotoropic distributions were assumed. 9458 1451 97 9458 1451 98 9458 1451 99 MF=15 Continuous photon energy spectra 9458 1451 100 MT=18 Fission 9458 1451 101 Experimental data measured by Verbinski et al./6/ for 9458 1451 102 Pu-239 thermal fission were adopted. 9458 1451 103 9458 1451 104 9458 1451 105 MF=31 Covariances of average number of neutrons per fission 9458 1451 106 MT=452 Number of neutrons per fission 9458 1451 107 Sum of covariances for MT=455 and MT=456. 9458 1451 108 9458 1451 109 MT=455 9458 1451 110 Error of 15% was assumed. 9458 1451 111 9458 1451 112 MT=456 9458 1451 113 Covariance was obtained by fitting a linear function to the 9458 1451 114 at 0.0 and 5.0 MeV with an uncertainty of 5%. 9458 1451 115 9458 1451 116 9458 1451 117 MF=33 Covariances of neutron cross sections 9458 1451 118 Covariances were given to all the cross sections by using 9458 1451 119 KALMAN code/7/ and the covariances of model parameters 9458 1451 120 used in the cross-section calculations. 9458 1451 121 9458 1451 122 For the following cross sections, standard deviations in the 9458 1451 123 energy region below 18 eV were assumed as follows: 9458 1451 124 9458 1451 125 Total 44 % 9458 1451 126 Elastic scattering 50 % 9458 1451 127 Fission 50 % 9458 1451 128 Capture 50 % 9458 1451 129 9458 1451 130 9458 1451 131 MF=34 Covariances for Angular Distributions 9458 1451 132 MT=2 Elastic scattering 9458 1451 133 Covariances were given only to P1 components. 9458 1451 134 9458 1451 135 9458 1451 136 MF=35 Covariances for Energy Distributions 9458 1451 137 MT=18 Fission spectra 9458 1451 138 Estimated with CCONE and KALMAN codes. 9458 1451 139 9458 1451 140 9458 1451 141 ***************************************************************** 9458 1451 142 Calculation with CCONE code 9458 1451 143 ***************************************************************** 9458 1451 144 9458 1451 145 Models and parameters used in the CCONE/4/ calculation 9458 1451 146 1) Coupled channel optical model 9458 1451 147 Levels in the rotational band were included. Optical model 9458 1451 148 potential and coupled levels are shown in Table 1. 9458 1451 149 9458 1451 150 2) Two-component exciton model/8/ 9458 1451 151 * Global parametrization of Koning-Duijvestijn/9/ 9458 1451 152 was used. 9458 1451 153 * Gamma emission channel/10/ was added to simulate direct 9458 1451 154 and semi-direct capture reaction. 9458 1451 155 9458 1451 156 3) Hauser-Feshbach statistical model 9458 1451 157 * Moldauer width fluctuation correction/11/ was included. 9458 1451 158 * Neutron, gamma and fission decay channel were included. 9458 1451 159 * Transmission coefficients of neutrons were taken from 9458 1451 160 coupled channel calculation in Table 1. 9458 1451 161 * The level scheme of the target is shown in Table 2. 9458 1451 162 * Level density formula of constant temperature and Fermi-gas 9458 1451 163 model were used with shell energy correction and collective 9458 1451 164 enhancement factor. Parameters are shown in Table 3. 9458 1451 165 * Fission channel: 9458 1451 166 Double humped fission barriers were assumed. 9458 1451 167 Fission barrier penetrabilities were calculated with 9458 1451 168 Hill-Wheler formula/12/. Fission barrier parameters were 9458 1451 169 shown in Table 4. Transition state model was used and 9458 1451 170 continuum levels are assumed above the saddles. The level 9458 1451 171 density parameters for inner and outer saddles are shown in 9458 1451 172 Tables 5 and 6, respectively. 9458 1451 173 * Gamma-ray strength function of Kopecky et al/13/,/14/ 9458 1451 174 was used. The prameters are shown in Table 7. 9458 1451 175 9458 1451 176 9458 1451 177 ------------------------------------------------------------------9458 1451 178 Tables 9458 1451 179 ------------------------------------------------------------------9458 1451 180 9458 1451 181 Table 1. Coupled channel calculation 9458 1451 182 -------------------------------------------------- 9458 1451 183 * rigid rotor model was applied 9458 1451 184 * coupled levels = 0,1,2,3,4 (see Table 2) 9458 1451 185 * optical potential parameters /5/ 9458 1451 186 Volume: 9458 1451 187 V_0 = 49.97 MeV 9458 1451 188 lambda_HF = 0.01004 1/MeV 9458 1451 189 C_viso = 15.9 MeV 9458 1451 190 A_v = 12.04 MeV 9458 1451 191 B_v = 81.36 MeV 9458 1451 192 E_a = 385 MeV 9458 1451 193 r_v = 1.2568 fm 9458 1451 194 a_v = 0.633 fm 9458 1451 195 Surface: 9458 1451 196 W_0 = 17.2 MeV 9458 1451 197 B_s = 11.19 MeV 9458 1451 198 C_s = 0.01361 1/MeV 9458 1451 199 C_wiso = 23.5 MeV 9458 1451 200 r_s = 1.1803 fm 9458 1451 201 a_s = 0.601 fm 9458 1451 202 Spin-orbit: 9458 1451 203 V_so = 5.75 MeV 9458 1451 204 lambda_so = 0.005 1/MeV 9458 1451 205 W_so = -3.1 MeV 9458 1451 206 B_so = 160 MeV 9458 1451 207 r_so = 1.1214 fm 9458 1451 208 a_so = 0.59 fm 9458 1451 209 Coulomb: 9458 1451 210 C_coul = 1.3 9458 1451 211 r_c = 1.2452 fm 9458 1451 212 a_c = 0.545 fm 9458 1451 213 Deformation: 9458 1451 214 beta_2 = 0.25113 9458 1451 215 beta_4 = 0.02211 9458 1451 216 beta_6 = -0.02816 9458 1451 217 9458 1451 218 * Calculated strength function 9458 1451 219 S0= 0.85e-4 S1= 2.57e-4 R'= 9.32 fm (En=1 keV) 9458 1451 220 -------------------------------------------------- 9458 1451 221 9458 1451 222 Table 2. Level Scheme of Pu-246 9458 1451 223 ------------------- 9458 1451 224 No. Ex(MeV) J PI 9458 1451 225 ------------------- 9458 1451 226 0 0.00000 0 + * 9458 1451 227 1 0.04600 2 + * 9458 1451 228 2 0.15500 4 + * 9458 1451 229 3 0.31790 6 + * 9458 1451 230 4 0.53500 8 + * 9458 1451 231 5 0.76900 1 - 9458 1451 232 6 0.90100 3 - 9458 1451 233 7 0.93800 10 + 9458 1451 234 8 0.99100 0 + 9458 1451 235 9 1.04000 4 + 9458 1451 236 ------------------- 9458 1451 237 *) Coupled levels in CC calculation 9458 1451 238 9458 1451 239 Table 3. Level density parameters 9458 1451 240 -------------------------------------------------------- 9458 1451 241 Nuclide a* Pair Eshell T E0 Ematch 9458 1451 242 1/MeV MeV MeV MeV MeV MeV 9458 1451 243 -------------------------------------------------------- 9458 1451 244 Pu-247 18.9645 0.7635 3.2067 0.3298 -0.4572 2.4635 9458 1451 245 Pu-246 18.8984 1.5302 3.1067 0.3332 0.2928 3.2528 9458 1451 246 Pu-245 18.8322 0.7667 2.7988 0.3349 -0.4502 2.4667 9458 1451 247 Pu-244 18.7661 1.5364 2.7670 0.3408 0.2726 3.2969 9458 1451 248 Pu-243 18.6999 0.7698 2.4578 0.3280 -0.3352 2.3315 9458 1451 249 -------------------------------------------------------- 9458 1451 250 9458 1451 251 Table 4. Fission barrier parameters 9458 1451 252 ---------------------------------------- 9458 1451 253 Nuclide V_A hw_A V_B hw_B 9458 1451 254 MeV MeV MeV MeV 9458 1451 255 ---------------------------------------- 9458 1451 256 Pu-247 5.600 0.530 5.300 0.520 9458 1451 257 Pu-246 6.000 1.040 4.700 0.600 9458 1451 258 Pu-245 5.600 0.530 5.300 0.520 9458 1451 259 Pu-244 6.000 1.040 4.700 0.600 9458 1451 260 Pu-243 5.750 0.680 5.520 0.520 9458 1451 261 ---------------------------------------- 9458 1451 262 9458 1451 263 Table 5. Level density above inner saddle 9458 1451 264 -------------------------------------------------------- 9458 1451 265 Nuclide a* Pair Eshell T E0 Ematch 9458 1451 266 1/MeV MeV MeV MeV MeV MeV 9458 1451 267 -------------------------------------------------------- 9458 1451 268 Pu-247 20.8609 0.8908 2.6000 0.3256 -1.5320 2.8908 9458 1451 269 Pu-246 20.7882 1.7852 2.6000 0.3263 -0.6376 3.7852 9458 1451 270 Pu-245 20.7155 0.8944 2.6000 0.3269 -1.5284 2.8944 9458 1451 271 Pu-244 20.6427 1.7925 2.6000 0.3275 -0.6303 3.7925 9458 1451 272 Pu-243 20.5699 0.8981 2.6000 0.3633 -2.0616 3.3981 9458 1451 273 -------------------------------------------------------- 9458 1451 274 9458 1451 275 Table 6. Level density above outer saddle 9458 1451 276 -------------------------------------------------------- 9458 1451 277 Nuclide a* Pair Eshell T E0 Ematch 9458 1451 278 1/MeV MeV MeV MeV MeV MeV 9458 1451 279 -------------------------------------------------------- 9458 1451 280 Pu-247 20.8609 0.8908 0.7000 0.3586 -0.8207 2.8908 9458 1451 281 Pu-246 20.7882 1.7852 0.6600 0.3597 0.0743 3.7852 9458 1451 282 Pu-245 20.7155 0.8944 0.6200 0.3609 -0.8159 2.8944 9458 1451 283 Pu-244 20.6427 1.7925 0.5800 0.3621 0.0827 3.7925 9458 1451 284 Pu-243 20.9439 0.8981 0.5400 0.3740 -0.9758 3.0981 9458 1451 285 -------------------------------------------------------- 9458 1451 286 9458 1451 287 Table 7. Gamma-ray strength function for Pu-247 9458 1451 288 -------------------------------------------------------- 9458 1451 289 K0 = 1.500 E0 = 4.500 (MeV) 9458 1451 290 * E1: ER = 10.90 (MeV) EG = 2.50 (MeV) SIG = 300.00 (mb) 9458 1451 291 ER = 13.80 (MeV) EG = 4.70 (MeV) SIG = 450.00 (mb) 9458 1451 292 * M1: ER = 6.53 (MeV) EG = 4.00 (MeV) SIG = 2.62 (mb) 9458 1451 293 * E2: ER = 10.04 (MeV) EG = 3.15 (MeV) SIG = 6.77 (mb) 9458 1451 294 -------------------------------------------------------- 9458 1451 295 9458 1451 296 9458 1451 297 References 9458 1451 298 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9458 1451 299 2) R.J.Tuttle: INDC(NDS)-107/G+Special, p.29 (1979). 9458 1451 300 3) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9458 1451 301 4) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9458 1451 302 5) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9458 1451 303 6) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9458 1451 304 7) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9458 1451 305 Japanese. 9458 1451 306 8) C.Kalbach: Phys. Rev. C33, 818 (1986). 9458 1451 307 9) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9458 1451 308 10) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9458 1451 309 11) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9458 1451 310 12) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9458 1451 311 13) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9458 1451 312 14) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9458 1451 313 9458 1451 314 1 451 328 19458 1451 315 2 151 4 19458 1451 316 3 4 26 19458 1451 317 3 16 13 19458 1451 318 3 17 10 19458 1451 319 3 18 121 19458 1451 320 3 37 6 19458 1451 321 3 102 169 19458 1451 322 8 4 2 19458 1451 323 8 16 2 19458 1451 324 8 17 2 19458 1451 325 8 18 2 19458 1451 326 8 37 2 19458 1451 327 8 102 2 19458 1451 328 9458 1 099999 9458 0 0 0 9.424600+4 2.439560+2 0 0 1 09458 2151 1 9.424600+4 1.000000+0 0 0 1 09458 2151 2 1.000000-5 1.800000+1 0 0 0 09458 2151 3 0.000000+0 9.320000-1 0 0 0 09458 2151 4 9458 2 099999 9458 0 0 0 9.424600+4 2.439560+2 0 0 0 09458 3 4 1 0.000000+0-4.600000+4 0 0 1 679458 3 4 2 67 2 9458 3 4 3 4.618860+4 0.000000+0 5.000000+4 6.232000-2 7.000000+4 3.307190-19458 3 4 4 1.000000+5 5.684160-1 1.159450+5 6.406862-1 1.300000+5 7.043979-19458 3 4 5 1.556350+5 8.036890-1 1.700000+5 8.567636-1 2.000000+5 9.727568-19458 3 4 6 3.000000+5 1.245033+0 3.192030+5 1.281837+0 4.000000+5 1.452883+09458 3 4 7 5.000000+5 1.711938+0 5.371930+5 1.782567+0 6.000000+5 1.900826+09458 3 4 8 7.000000+5 2.103619+0 7.721520+5 2.191586+0 8.000000+5 2.269620+09458 3 4 9 9.000000+5 2.428669+0 9.046930+5 2.433624+0 9.418450+5 2.478335+09458 3 4 10 9.950620+5 2.519368+0 1.000000+6 2.525335+0 1.044260+6 2.533140+09458 3 4 11 1.100000+6 2.522459+0 1.300000+6 2.504091+0 1.600000+6 2.704808+09458 3 4 12 1.800000+6 2.852025+0 2.000000+6 2.971972+0 2.300000+6 3.089859+09458 3 4 13 2.500000+6 3.130654+0 2.700000+6 3.151084+0 3.000000+6 3.179245+09458 3 4 14 3.500000+6 3.156115+0 4.000000+6 3.111641+0 4.500000+6 3.054973+09458 3 4 15 5.000000+6 2.963745+0 5.500000+6 2.761667+0 6.000000+6 2.395815+09458 3 4 16 6.500000+6 1.857041+0 7.000000+6 1.436297+0 7.500000+6 1.149972+09458 3 4 17 8.000000+6 9.859678-1 8.500000+6 8.747409-1 9.000000+6 8.024449-19458 3 4 18 9.500000+6 7.421361-1 1.000000+7 7.019158-1 1.050000+7 6.632581-19458 3 4 19 1.100000+7 6.345509-1 1.150000+7 6.047247-1 1.200000+7 5.781616-19458 3 4 20 1.250000+7 5.537063-1 1.300000+7 5.298597-1 1.350000+7 5.069449-19458 3 4 21 1.400000+7 4.869898-1 1.450000+7 4.704636-1 1.500000+7 4.512947-19458 3 4 22 1.550000+7 4.340161-1 1.600000+7 4.196512-1 1.650000+7 4.029751-19458 3 4 23 1.700000+7 3.910344-1 1.750000+7 3.774038-1 1.800000+7 3.666441-19458 3 4 24 1.850000+7 3.545534-1 1.900000+7 3.458333-1 1.950000+7 3.374125-19458 3 4 25 2.000000+7 3.266873-1 9458 3 4 26 9458 3 099999 9.424600+4 2.439560+2 0 0 0 09458 3 16 1 -5.782200+6-5.782200+6 0 0 1 309458 3 16 2 30 2 9458 3 16 3 5.805900+6 0.000000+0 6.000000+6 2.238980-2 6.500000+6 3.953490-19458 3 16 4 7.000000+6 8.368550-1 7.500000+6 1.203970+0 8.000000+6 1.385320+09458 3 16 5 8.500000+6 1.504320+0 9.000000+6 1.590490+0 9.500000+6 1.645160+09458 3 16 6 1.000000+7 1.666710+0 1.050000+7 1.695200+0 1.100000+7 1.704630+09458 3 16 7 1.150000+7 1.685670+0 1.200000+7 1.584870+0 1.250000+7 1.421910+09458 3 16 8 1.300000+7 1.227770+0 1.350000+7 1.026350+0 1.400000+7 8.757670-19458 3 16 9 1.450000+7 7.186520-1 1.500000+7 6.169510-1 1.550000+7 5.408760-19458 3 16 10 1.600000+7 4.718800-1 1.650000+7 4.301230-1 1.700000+7 3.858830-19458 3 16 11 1.750000+7 3.623560-1 1.800000+7 3.341050-1 1.850000+7 3.221680-19458 3 16 12 1.900000+7 3.027230-1 1.950000+7 2.826170-1 2.000000+7 2.764090-19458 3 16 13 9458 3 099999 9.424600+4 2.439560+2 0 0 0 09458 3 17 1 -1.055300+7-1.055300+7 0 0 1 199458 3 17 2 19 2 9458 3 17 3 1.059630+7 0.000000+0 1.150000+7 2.593760-2 1.200000+7 1.232040-19458 3 17 4 1.250000+7 2.440580-1 1.300000+7 3.517560-1 1.350000+7 4.550160-19458 3 17 5 1.400000+7 4.931230-1 1.450000+7 5.735480-1 1.500000+7 6.043170-19458 3 17 6 1.550000+7 6.351650-1 1.600000+7 6.681430-1 1.650000+7 6.981080-19458 3 17 7 1.700000+7 7.324790-1 1.750000+7 7.594290-1 1.800000+7 7.665070-19458 3 17 8 1.850000+7 7.711150-1 1.900000+7 7.456520-1 1.950000+7 7.066310-19458 3 17 9 2.000000+7 6.668260-1 9458 3 17 10 9458 3 099999 9.424600+4 2.439560+2 0 0 0 09458 3 18 1 2.071000+8 2.071000+8 0 0 1 3539458 3 18 2 353 2 9458 3 18 3 1.000000-5 1.603001-1 1.103037-5 1.526303-1 1.216691-5 1.453276-19458 3 18 4 1.342055-5 1.383743-1 1.480336-5 1.317538-1 1.632865-5 1.254501-19458 3 18 5 1.801111-5 1.194482-1 1.986691-5 1.137334-1 2.191394-5 1.082921-19458 3 18 6 2.417189-5 1.031113-1 2.666248-5 9.817839-2 2.940971-5 9.348158-29458 3 18 7 3.243999-5 8.900956-2 3.578251-5 8.475157-2 3.946943-5 8.069738-29458 3 18 8 4.353624-5 7.683722-2 4.802208-5 7.316183-2 5.297013-5 6.966235-29458 3 18 9 5.842801-5 6.633036-2 6.444825-5 6.315786-2 7.108881-5 6.013721-29458 3 18 10 7.841358-5 5.726113-2 8.649308-5 5.452272-2 9.540506-5 5.191537-29458 3 18 11 1.052353-4 4.943282-2 1.160784-4 4.706909-2 1.280388-4 4.481849-29458 3 18 12 1.412315-4 4.267560-2 1.557836-4 4.063527-2 1.718351-4 3.869257-29458 3 18 13 1.895404-4 3.684284-2 2.090701-4 3.508161-2 2.306120-4 3.340466-29458 3 18 14 2.543736-4 3.180793-2 2.805835-4 3.028758-2 3.094939-4 2.883996-29458 3 18 15 3.413832-4 2.746158-2 3.765583-4 2.614912-2 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