JENDL-5 (Neutron sublibrary (activation cs)) Cm-241 0 0 0 0 9.624100+4 2.389870+2 0 0 6 19628 1451 1 0.000000+0 1.000000+0 0 0 0 69628 1451 2 1.000000+0 2.000000+7 0 0 10 59628 1451 3 2.936000+2 0.000000+0 4 0 313 129628 1451 4 96-Cm-241 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9628 1451 5 DIST-DEC21 20100304 9628 1451 6 ----JENDL-5 MATERIAL 9628 9628 1451 7 -----INCIDENT NEUTRON DATA 9628 1451 8 ------ENDF-6 FORMAT 9628 1451 9 9628 1451 10 History 9628 1451 11 07-08 Theoretical calculation was performed with CCONE code. 9628 1451 12 07-11 Theoretical calculation was performed with CCONE code. 9628 1451 13 Data were compiled as JENDL/AC-2008/1/. 9628 1451 14 10-02 Data of prompt gamma rays due to fission were given. 9628 1451 15 10-03 Covariance data were given. 9628 1451 16 9628 1451 17 21-11 revised by O.Iwamoto 9628 1451 18 (MF3/MT19-21,38) deleted 9628 1451 19 (MF8/MT4,16-18,102) added 9628 1451 20 9628 1451 21 MF=1 General information 9628 1451 22 MT=452 Number of Neutrons per fission 9628 1451 23 Sum of MT's=455 and 456. 9628 1451 24 9628 1451 25 MT=455 Delayed neutron data 9628 1451 26 (Same as JENDL-3.3) 9628 1451 27 Estimated from Tuttle's systematics/2/. 9628 1451 28 9628 1451 29 MT=456 Number of prompt neutrons per fission 9628 1451 30 (Same as JENDL-3.3) 9628 1451 31 Estimated from Howerton's sytematics/3/. 9628 1451 32 9628 1451 33 9628 1451 34 MF= 2 Resonance parameters 9628 1451 35 MT=151 9628 1451 36 No resonance parameters are given. 9628 1451 37 9628 1451 38 9628 1451 39 Thermal cross sections and resonance integrals (at 300K) 9628 1451 40 ------------------------------------------------------- 9628 1451 41 0.0253 eV reson. integ.(*) 9628 1451 42 (barns) (barns) 9628 1451 43 ------------------------------------------------------- 9628 1451 44 total 1211.2 9628 1451 45 elastic 10.62 9628 1451 46 fission 1000.3 854 9628 1451 47 capture 200.1 79.4 9628 1451 48 ------------------------------------------------------- 9628 1451 49 (*) In the energy range from 0.5 eV to 10 MeV. 9628 1451 50 9628 1451 51 9628 1451 52 MF= 3 Neutron cross sections 9628 1451 53 Below 1.1 eV: 9628 1451 54 * Elastic scattering cross section is 10.6 b calculated from 9628 1451 55 scattering radius of 9.188 fm/4/. 9628 1451 56 * Capture cross section is in the 1/v shape, and 200 b at 9628 1451 57 0.0253 eV which was estimated from systematics. 9628 1451 58 * Fission cross section is in the 1/v shape, and 1000 b at 9628 1451 59 0.0253 eV which was estimated from systematics. 9628 1451 60 9628 1451 61 Above 1.1 eV: 9628 1451 62 Cross sections were calculated with CCONE code/4/. 9628 1451 63 9628 1451 64 MT= 1 Total cross section 9628 1451 65 The cross section was calculated with CC OMP of Soukhovitskii 9628 1451 66 et al./5/. 9628 1451 67 9628 1451 68 MT=18 Fission cross section 9628 1451 69 The simulated (n,f) cross sections of Britt and Wilhelmy/6/ 9628 1451 70 were used to determine the parameters in the CCONE 9628 1451 71 calculation. 9628 1451 72 9628 1451 73 9628 1451 74 MF= 4 Angular distributions of secondary neutrons 9628 1451 75 MT=2 Elastic scattering 9628 1451 76 Calculated with CCONE code. 9628 1451 77 9628 1451 78 MT=18 Fission 9628 1451 79 Isotropic distributions in the laboratory system were assumed.9628 1451 80 9628 1451 81 9628 1451 82 MF= 5 Energy distributions of secondary neutrons 9628 1451 83 MT=18 Prompt neutrons 9628 1451 84 Calculated with CCONE code/4/. 9628 1451 85 9628 1451 86 9628 1451 87 MF= 6 Energy-angle distributions 9628 1451 88 Calculated with CCONE code. 9628 1451 89 Distributions from fission (MT=18) are not included. 9628 1451 90 9628 1451 91 9628 1451 92 MF=12 Photon production multiplicities 9628 1451 93 MT=18 Fission 9628 1451 94 Calculated from the total energy released by the prompt 9628 1451 95 gamma-rays due to fission which was estimated from its 9628 1451 96 systematics, and the average energy of gamma-rays. 9628 1451 97 9628 1451 98 9628 1451 99 MF=14 Photon angular distributions 9628 1451 100 MT=18 Fission 9628 1451 101 Isotoropic distributions were assumed. 9628 1451 102 9628 1451 103 9628 1451 104 MF=15 Continuous photon energy spectra 9628 1451 105 MT=18 Fission 9628 1451 106 Experimental data measured by Verbinski et al./7/ for 9628 1451 107 Pu-239 thermal fission were adopted. 9628 1451 108 9628 1451 109 9628 1451 110 MF=31 Covariances of average number of neutrons per fission 9628 1451 111 MT=452 Number of neutrons per fission 9628 1451 112 Sum of covariances for MT=455 and MT=456. 9628 1451 113 9628 1451 114 MT=455 9628 1451 115 Error of 15% was assumed. 9628 1451 116 9628 1451 117 MT=456 9628 1451 118 Covariance was obtained by fitting a linear function to the 9628 1451 119 at 0.0 and 5.0 MeV with an uncertainty of 5%. 9628 1451 120 9628 1451 121 9628 1451 122 MF=33 Covariances of neutron cross sections 9628 1451 123 Covariances were given to all the cross sections by using 9628 1451 124 KALMAN code/8/ and the covariances of model parameters 9628 1451 125 used in the cross-section calculations. 9628 1451 126 9628 1451 127 Covariances of the fission cross section were determined from 9628 1451 128 experimental data. 9628 1451 129 9628 1451 130 For the following cross sections, standard deviations in the 9628 1451 131 energy region below 1.1 eV were assumed as follows: 9628 1451 132 9628 1451 133 Total 42 % 9628 1451 134 Elastic scattering 50 % 9628 1451 135 Fission 50 % 9628 1451 136 Capture 50 % 9628 1451 137 9628 1451 138 9628 1451 139 MF=34 Covariances for Angular Distributions 9628 1451 140 MT=2 Elastic scattering 9628 1451 141 Covariances were given only to P1 components. 9628 1451 142 9628 1451 143 9628 1451 144 MF=35 Covariances for Energy Distributions 9628 1451 145 MT=18 Fission spectra 9628 1451 146 Estimated with CCONE and KALMAN codes. 9628 1451 147 9628 1451 148 9628 1451 149 ***************************************************************** 9628 1451 150 Calculation with CCONE code 9628 1451 151 ***************************************************************** 9628 1451 152 9628 1451 153 Models and parameters used in the CCONE/4/ calculation 9628 1451 154 1) Coupled channel optical model 9628 1451 155 Levels in the rotational band were included. Optical model 9628 1451 156 potential and coupled levels are shown in Table 1. 9628 1451 157 9628 1451 158 2) Two-component exciton model/9/ 9628 1451 159 * Global parametrization of Koning-Duijvestijn/10/ 9628 1451 160 was used. 9628 1451 161 * Gamma emission channel/11/ was added to simulate direct 9628 1451 162 and semi-direct capture reaction. 9628 1451 163 9628 1451 164 3) Hauser-Feshbach statistical model 9628 1451 165 * Moldauer width fluctuation correction/12/ was included. 9628 1451 166 * Neutron, gamma and fission decay channel were included. 9628 1451 167 * Transmission coefficients of neutrons were taken from 9628 1451 168 coupled channel calculation in Table 1. 9628 1451 169 * The level scheme of the target is shown in Table 2. 9628 1451 170 * Level density formula of constant temperature and Fermi-gas 9628 1451 171 model were used with shell energy correction and collective 9628 1451 172 enhancement factor. Parameters are shown in Table 3. 9628 1451 173 * Fission channel: 9628 1451 174 Double humped fission barriers were assumed. 9628 1451 175 Fission barrier penetrabilities were calculated with 9628 1451 176 Hill-Wheler formula/13/. Fission barrier parameters were 9628 1451 177 shown in Table 4. Transition state model was used and 9628 1451 178 continuum levels are assumed above the saddles. The level 9628 1451 179 density parameters for inner and outer saddles are shown in 9628 1451 180 Tables 5 and 6, respectively. 9628 1451 181 * Gamma-ray strength function of Kopecky et al/14/,/15/ 9628 1451 182 was used. The prameters are shown in Table 7. 9628 1451 183 9628 1451 184 9628 1451 185 ------------------------------------------------------------------9628 1451 186 Tables 9628 1451 187 ------------------------------------------------------------------9628 1451 188 9628 1451 189 Table 1. Coupled channel calculation 9628 1451 190 -------------------------------------------------- 9628 1451 191 * rigid rotor model was applied 9628 1451 192 * coupled levels = 0,1,2,3,4 (see Table 2) 9628 1451 193 * optical potential parameters /5/ 9628 1451 194 Volume: 9628 1451 195 V_0 = 49.97 MeV 9628 1451 196 lambda_HF = 0.01004 1/MeV 9628 1451 197 C_viso = 15.9 MeV 9628 1451 198 A_v = 12.04 MeV 9628 1451 199 B_v = 81.36 MeV 9628 1451 200 E_a = 385 MeV 9628 1451 201 r_v = 1.2568 fm 9628 1451 202 a_v = 0.633 fm 9628 1451 203 Surface: 9628 1451 204 W_0 = 17.2 MeV 9628 1451 205 B_s = 11.19 MeV 9628 1451 206 C_s = 0.01361 1/MeV 9628 1451 207 C_wiso = 23.5 MeV 9628 1451 208 r_s = 1.1803 fm 9628 1451 209 a_s = 0.601 fm 9628 1451 210 Spin-orbit: 9628 1451 211 V_so = 5.75 MeV 9628 1451 212 lambda_so = 0.005 1/MeV 9628 1451 213 W_so = -3.1 MeV 9628 1451 214 B_so = 160 MeV 9628 1451 215 r_so = 1.1214 fm 9628 1451 216 a_so = 0.59 fm 9628 1451 217 Coulomb: 9628 1451 218 C_coul = 1.3 9628 1451 219 r_c = 1.2452 fm 9628 1451 220 a_c = 0.545 fm 9628 1451 221 Deformation: 9628 1451 222 beta_2 = 0.213 9628 1451 223 beta_4 = 0.066 9628 1451 224 beta_6 = 0.0015 9628 1451 225 9628 1451 226 * Calculated strength function 9628 1451 227 S0= 0.95e-4 S1= 3.33e-4 R'= 9.19 fm (En=1 keV) 9628 1451 228 -------------------------------------------------- 9628 1451 229 9628 1451 230 Table 2. Level Scheme of Cm-241 9628 1451 231 ------------------- 9628 1451 232 No. Ex(MeV) J PI 9628 1451 233 ------------------- 9628 1451 234 0 0.00000 1/2 + * 9628 1451 235 1 0.00550 3/2 + * 9628 1451 236 2 0.05710 5/2 + * 9628 1451 237 3 0.08100 7/2 + * 9628 1451 238 4 0.16300 9/2 + * 9628 1451 239 ------------------- 9628 1451 240 *) Coupled levels in CC calculation 9628 1451 241 9628 1451 242 Table 3. Level density parameters 9628 1451 243 -------------------------------------------------------- 9628 1451 244 Nuclide a* Pair Eshell T E0 Ematch 9628 1451 245 1/MeV MeV MeV MeV MeV MeV 9628 1451 246 -------------------------------------------------------- 9628 1451 247 Cm-242 18.6337 1.5428 1.3581 0.3517 0.3362 3.2428 9628 1451 248 Cm-241 18.5675 0.7730 1.0938 0.3935 -0.8080 2.9546 9628 1451 249 Cm-240 18.5012 1.5492 1.2421 0.3627 0.2677 3.3492 9628 1451 250 Cm-239 18.4349 0.7762 1.2849 0.2896 0.0935 1.7762 9628 1451 251 Cm-238 18.3685 1.5557 1.3566 0.2895 0.8738 2.5557 9628 1451 252 -------------------------------------------------------- 9628 1451 253 9628 1451 254 Table 4. Fission barrier parameters 9628 1451 255 ---------------------------------------- 9628 1451 256 Nuclide V_A hw_A V_B hw_B 9628 1451 257 MeV MeV MeV MeV 9628 1451 258 ---------------------------------------- 9628 1451 259 Cm-242 6.250 1.040 5.700 0.800 9628 1451 260 Cm-241 5.800 0.800 6.200 0.600 9628 1451 261 Cm-240 6.000 1.040 5.000 0.600 9628 1451 262 Cm-239 6.300 0.800 5.000 0.520 9628 1451 263 Cm-238 6.000 1.040 5.000 0.600 9628 1451 264 ---------------------------------------- 9628 1451 265 9628 1451 266 Table 5. Level density above inner saddle 9628 1451 267 -------------------------------------------------------- 9628 1451 268 Nuclide a* Pair Eshell T E0 Ematch 9628 1451 269 1/MeV MeV MeV MeV MeV MeV 9628 1451 270 -------------------------------------------------------- 9628 1451 271 Cm-242 20.4971 1.7999 2.6000 0.3433 -0.8376 3.9999 9628 1451 272 Cm-241 20.4242 0.9018 2.6000 0.3647 -2.0579 3.4018 9628 1451 273 Cm-240 20.3513 1.8074 2.6000 0.3300 -0.6156 3.8074 9628 1451 274 Cm-239 20.2784 0.9056 2.6000 0.3307 -1.5174 2.9056 9628 1451 275 Cm-238 20.2054 1.8150 2.6000 0.3313 -0.6081 3.8150 9628 1451 276 -------------------------------------------------------- 9628 1451 277 9628 1451 278 Table 6. Level density above outer saddle 9628 1451 279 -------------------------------------------------------- 9628 1451 280 Nuclide a* Pair Eshell T E0 Ematch 9628 1451 281 1/MeV MeV MeV MeV MeV MeV 9628 1451 282 -------------------------------------------------------- 9628 1451 283 Cm-242 22.7331 1.7999 0.6200 0.3788 -0.3562 4.3499 9628 1451 284 Cm-241 20.4242 0.9018 0.5800 0.3862 -1.0599 3.2018 9628 1451 285 Cm-240 20.3513 1.8074 0.5400 0.3656 0.0996 3.8074 9628 1451 286 Cm-239 20.2784 0.9056 0.5000 0.3668 -0.8017 2.9056 9628 1451 287 Cm-238 20.2054 1.8150 0.4600 0.3680 0.1083 3.8150 9628 1451 288 -------------------------------------------------------- 9628 1451 289 9628 1451 290 Table 7. Gamma-ray strength function for Cm-242 9628 1451 291 -------------------------------------------------------- 9628 1451 292 * E1: ER = 11.53 (MeV) EG = 2.77 (MeV) SIG = 318.90 (mb) 9628 1451 293 ER = 14.32 (MeV) EG = 4.20 (MeV) SIG = 421.74 (mb) 9628 1451 294 * M1: ER = 6.58 (MeV) EG = 4.00 (MeV) SIG = 1.40 (mb) 9628 1451 295 * E2: ER = 10.11 (MeV) EG = 3.21 (MeV) SIG = 7.07 (mb) 9628 1451 296 -------------------------------------------------------- 9628 1451 297 9628 1451 298 9628 1451 299 References 9628 1451 300 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9628 1451 301 2) R.J.Tuttle: INDC(NDS)-107/G+Special, p.29 (1979). 9628 1451 302 3) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9628 1451 303 4) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9628 1451 304 5) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9628 1451 305 6) H.C.Britt, J.B.Wilhelmy: Nucl. Sci. Eng., 72, 222 (1979). 9628 1451 306 7) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9628 1451 307 8) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9628 1451 308 Japanese. 9628 1451 309 9) C.Kalbach: Phys. Rev. C33, 818 (1986). 9628 1451 310 10) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9628 1451 311 11) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9628 1451 312 12) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9628 1451 313 13) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9628 1451 314 14) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9628 1451 315 15) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9628 1451 316 9628 1451 317 1 451 329 19628 1451 318 2 151 4 19628 1451 319 3 4 28 19628 1451 320 3 16 13 19628 1451 321 3 17 8 19628 1451 322 3 18 120 19628 1451 323 3 102 139 19628 1451 324 8 4 2 19628 1451 325 8 16 2 19628 1451 326 8 17 2 19628 1451 327 8 18 2 19628 1451 328 8 102 2 19628 1451 329 9628 1 099999 9628 0 0 0 9.624100+4 2.389870+2 0 0 1 09628 2151 1 9.624100+4 1.000000+0 0 0 1 09628 2151 2 1.000000-5 1.100000+0 0 0 0 09628 2151 3 5.000000-1 9.188000-1 0 0 0 09628 2151 4 9628 2 099999 9628 0 0 0 9.624100+4 2.389870+2 0 0 0 09628 3 4 1 0.000000+0-5.500000+3 0 0 1 749628 3 4 2 74 2 9628 3 4 3 5.523010+3 0.000000+0 7.000000+3 5.353760-2 1.000000+4 7.600880-29628 3 4 4 2.000000+4 1.030100-1 3.000000+4 1.304750-1 5.000000+4 1.987190-19628 3 4 5 5.733890+4 2.253750-1 7.000000+4 2.856499-1 8.133890+4 3.445337-19628 3 4 6 1.000000+5 4.471164-1 1.109220+5 5.014108-1 1.200000+5 5.465396-19628 3 4 7 1.400000+5 6.355649-1 1.636820+5 7.272161-1 1.700000+5 7.493907-19628 3 4 8 2.000000+5 8.432180-1 2.500000+5 9.303663-1 3.000000+5 1.044904+09628 3 4 9 4.000000+5 1.203441+0 5.000000+5 1.353018+0 6.000000+5 1.490919+09628 3 4 10 7.000000+5 1.602631+0 8.000000+5 1.708152+0 9.000000+5 1.792638+09628 3 4 11 1.000000+6 1.859780+0 1.100000+6 1.918219+0 1.200000+6 1.964977+09628 3 4 12 1.300000+6 1.997836+0 1.400000+6 2.024231+0 1.500000+6 2.034442+09628 3 4 13 1.600000+6 2.040640+0 1.700000+6 2.032156+0 1.800000+6 2.021281+09628 3 4 14 1.900000+6 1.999014+0 2.000000+6 1.975463+0 2.100000+6 1.943032+09628 3 4 15 2.300000+6 1.876866+0 2.500000+6 1.801273+0 2.700000+6 1.726126+09628 3 4 16 3.000000+6 1.671337+0 3.500000+6 1.550686+0 4.000000+6 1.462605+09628 3 4 17 4.500000+6 1.416221+0 5.000000+6 1.375015+0 5.500000+6 1.360295+09628 3 4 18 6.000000+6 1.341557+0 6.500000+6 1.250520+0 7.000000+6 1.064290+09628 3 4 19 7.500000+6 9.149437-1 8.000000+6 8.108872-1 8.500000+6 7.352523-19628 3 4 20 9.000000+6 6.814761-1 9.500000+6 6.392391-1 1.000000+7 6.054427-19628 3 4 21 1.050000+7 5.771390-1 1.100000+7 5.524817-1 1.150000+7 5.302151-19628 3 4 22 1.200000+7 5.098877-1 1.250000+7 4.911110-1 1.300000+7 4.729417-19628 3 4 23 1.350000+7 4.561066-1 1.400000+7 4.398387-1 1.450000+7 4.243619-19628 3 4 24 1.500000+7 4.093020-1 1.550000+7 3.956393-1 1.600000+7 3.820658-19628 3 4 25 1.650000+7 3.697122-1 1.700000+7 3.579489-1 1.750000+7 3.465443-19628 3 4 26 1.800000+7 3.364978-1 1.850000+7 3.263638-1 1.900000+7 3.174689-19628 3 4 27 1.950000+7 3.088469-1 2.000000+7 3.004261-1 9628 3 4 28 9628 3 099999 9.624100+4 2.389870+2 0 0 0 09628 3 16 1 -6.093330+6-6.093330+6 0 0 1 299628 3 16 2 29 2 9628 3 16 3 6.118820+6 0.000000+0 6.500000+6 1.768440-2 7.000000+6 8.726790-29628 3 16 4 7.500000+6 1.294430-1 8.000000+6 1.420220-1 8.500000+6 1.534920-19628 3 16 5 9.000000+6 1.578200-1 9.500000+6 1.641500-1 1.000000+7 1.729900-19628 3 16 6 1.050000+7 1.816700-1 1.100000+7 1.949830-1 1.150000+7 2.071230-19628 3 16 7 1.200000+7 2.146630-1 1.250000+7 2.137180-1 1.300000+7 2.045720-19628 3 16 8 1.350000+7 1.907560-1 1.400000+7 1.754070-1 1.450000+7 1.619150-19628 3 16 9 1.500000+7 1.480640-1 1.550000+7 1.380500-1 1.600000+7 1.305050-19628 3 16 10 1.650000+7 1.222090-1 1.700000+7 1.172300-1 1.750000+7 1.137190-19628 3 16 11 1.800000+7 1.081130-1 1.850000+7 1.057000-1 1.900000+7 1.012820-19628 3 16 12 1.950000+7 9.689980-2 2.000000+7 9.565220-2 9628 3 16 13 9628 3 099999 9.624100+4 2.389870+2 0 0 0 09628 3 17 1 -1.363120+7-1.363120+7 0 0 1 139628 3 17 2 13 2 9628 3 17 3 1.368820+7 0.000000+0 1.450000+7 1.061510-5 1.500000+7 8.588930-59628 3 17 4 1.550000+7 1.952420-4 1.600000+7 4.747040-4 1.650000+7 7.768190-49628 3 17 5 1.700000+7 1.193020-3 1.750000+7 1.781730-3 1.800000+7 2.579040-39628 3 17 6 1.850000+7 3.601510-3 1.900000+7 4.841930-3 1.950000+7 6.285440-39628 3 17 7 2.000000+7 7.908370-3 9628 3 17 8 9628 3 099999 9.624100+4 2.389870+2 0 0 0 09628 3 18 1 2.020000+8 2.020000+8 0 0 1 3519628 3 18 2 351 2 9628 3 18 3 1.000000-5 5.009450+4 1.103037-5 4.769766+4 1.216691-5 4.541552+49628 3 18 4 1.342055-5 4.324259+4 1.480336-5 4.117365+4 1.632865-5 3.920372+49628 3 18 5 1.801111-5 3.732806+4 1.986691-5 3.554217+4 2.191394-5 3.384175+49628 3 18 6 2.417189-5 3.222270+4 2.666248-5 3.068115+4 2.940971-5 2.921337+49628 3 18 7 3.243999-5 2.781584+4 3.578251-5 2.648519+4 3.946943-5 2.521823+49628 3 18 8 4.353624-5 2.401192+4 4.802208-5 2.286333+4 5.297013-5 2.176973+49628 3 18 9 5.842801-5 2.072846+4 6.444825-5 1.973704+4 7.108881-5 1.879307+49628 3 18 10 7.841358-5 1.789428+4 8.649308-5 1.703851+4 9.540506-5 1.622370+49628 3 18 11 1.052353-4 1.544789+4 1.160784-4 1.470921+4 1.280388-4 1.400588+49628 3 18 12 1.412315-4 1.333622+4 1.557836-4 1.269860+4 1.718351-4 1.209150+49628 3 18 13 1.895404-4 1.151345+4 2.090701-4 1.096306+4 2.306120-4 1.043900+49628 3 18 14 2.543736-4 9.940019+3 2.805835-4 9.464905+3 3.094939-4 9.012518+39628 3 18 15 3.413832-4 8.581769+3 3.765583-4 8.171621+3 4.153577-4 7.781087+39628 3 18 16 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