JENDL-5 (Neutron sublibrary (activation cs)) Ac-226 0 0 0 0 8.922600+4 2.240840+2 0 0 6 18928 1451 1 0.000000+0 1.000000+0 0 0 0 68928 1451 2 1.000000+0 2.000000+7 0 0 10 58928 1451 3 2.936000+2 0.000000+0 4 0 307 148928 1451 4 89-Ac-226 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 8928 1451 5 DIST-DEC21 20100303 8928 1451 6 ----JENDL-5 MATERIAL 8928 8928 1451 7 -----INCIDENT NEUTRON DATA 8928 1451 8 ------ENDF-6 FORMAT 8928 1451 9 8928 1451 10 History 8928 1451 11 07-10 Theoretical calculation was performed with CCONE code. 8928 1451 12 Data were compiled as JENDL/AC-2008/1/. 8928 1451 13 10-02 Data of prompt gamma rays due to fission were given. 8928 1451 14 10-03 Covariance data were given. 8928 1451 15 21-11 revised by O.Iwamoto 8928 1451 16 (MF3/MT19-21,38) deleted 8928 1451 17 (MF8/MT4,16-18,37,102) added 8928 1451 18 8928 1451 19 MF=1 General information 8928 1451 20 MT=452 Number of Neutrons per fission 8928 1451 21 Sum of MT's=455 and 456. 8928 1451 22 8928 1451 23 MT=455 Delayed neutron data 8928 1451 24 Estimated from systematics by Tuttle/2/, Benedetti et al./3/ 8928 1451 25 and Waldo et al./4/ 8928 1451 26 8928 1451 27 MT=456 Number of prompt neutrons per fission 8928 1451 28 Estimated from Howerton's systematics/5/. 8928 1451 29 8928 1451 30 8928 1451 31 MF= 2 Resonance parameters 8928 1451 32 MT=151 8928 1451 33 No resonance parameters are given. 8928 1451 34 8928 1451 35 8928 1451 36 Thermal cross sections and resonance integrals (at 300K) 8928 1451 37 ------------------------------------------------------- 8928 1451 38 0.0253 eV reson. integ.(*) 8928 1451 39 (barns) (barns) 8928 1451 40 ------------------------------------------------------- 8928 1451 41 total 1015.4 8928 1451 42 elastic 12.63 8928 1451 43 fission 2.001 8.61 8928 1451 44 capture 1000.4 1190 8928 1451 45 ------------------------------------------------------- 8928 1451 46 (*) In the energy range from 0.5 eV to 10 MeV. 8928 1451 47 8928 1451 48 8928 1451 49 MF= 3 Neutron cross sections 8928 1451 50 Below 0.3 eV: 8928 1451 51 * Elastic scattering cross section is 12.6b calculated from 8928 1451 52 scattering radius of 9.998 fm/6/. 8928 1451 53 * Fission cross section is in the 1/v shape. 8928 1451 54 2 b at 0.0253 eV was estimated from systematics. 8928 1451 55 * Capture cross section is in the 1/v shape. 8928 1451 56 1000 b at 0.0253 eV was estimated from systematics. 8928 1451 57 8928 1451 58 Above 0.3 eV: 8928 1451 59 Cross sections were calculated with CCONE code/6/. 8928 1451 60 8928 1451 61 MT=1 Total cross section 8928 1451 62 The cross section was calculated with CC OMP of Soukhovitskii 8928 1451 63 et al./7/. 8928 1451 64 8928 1451 65 8928 1451 66 MF= 4 Angular distributions of secondary neutrons 8928 1451 67 MT=2 Elastic scattering 8928 1451 68 Calculated with CCONE code/6/. 8928 1451 69 8928 1451 70 MT=18 Fission 8928 1451 71 Isotropic distributions in the laboratory system were assumed.8928 1451 72 8928 1451 73 8928 1451 74 MF= 5 Energy distributions of secondary neutrons 8928 1451 75 MT=18 Prompt neutrons 8928 1451 76 Calculated with CCONE code/6/. 8928 1451 77 8928 1451 78 8928 1451 79 MF= 6 Energy-angle distributions 8928 1451 80 Calculated with CCONE code/6/. 8928 1451 81 Distributions from fission (MT=18) are not included. 8928 1451 82 8928 1451 83 8928 1451 84 MF=12 Photon production multiplicities 8928 1451 85 MT=18 Fission 8928 1451 86 Calculated from the total energy released by the prompt 8928 1451 87 gamma-rays due to fission which was estimated from its 8928 1451 88 systematics, and the average energy of gamma-rays. 8928 1451 89 8928 1451 90 8928 1451 91 MF=14 Photon angular distributions 8928 1451 92 MT=18 Fission 8928 1451 93 Isotoropic distributions were assumed. 8928 1451 94 8928 1451 95 8928 1451 96 MF=15 Continuous photon energy spectra 8928 1451 97 MT=18 Fission 8928 1451 98 Experimental data measured by Verbinski et al./8/ for 8928 1451 99 U-235 thermal fission were adopted. 8928 1451 100 8928 1451 101 8928 1451 102 MF=31 Covariances of average number of neutrons per fission 8928 1451 103 MT=452 Number of neutrons per fission 8928 1451 104 Sum of covariances for MT=455 and MT=456. 8928 1451 105 8928 1451 106 MT=455 8928 1451 107 Error of 15% was assumed. 8928 1451 108 8928 1451 109 MT=456 8928 1451 110 Covariance was obtained by fitting a linear function to the 8928 1451 111 at 0.0 and 5.0 MeV with an uncertainty of 5%. 8928 1451 112 8928 1451 113 8928 1451 114 MF=33 Covariances of neutron cross sections 8928 1451 115 Covariances were given to all the cross sections by using 8928 1451 116 KALMAN code/9/ and the covariances of model parameters 8928 1451 117 used in the cross-section calculations. 8928 1451 118 8928 1451 119 For the following cross sections, standard deviations in the 8928 1451 120 energy region below 0.3 eV were assumed as follows: 8928 1451 121 8928 1451 122 Total 49 % 8928 1451 123 Elastic scattering 50 % 8928 1451 124 Fission 50 % 8928 1451 125 Capture 50 % 8928 1451 126 8928 1451 127 8928 1451 128 MF=34 Covariances for Angular Distributions 8928 1451 129 MT=2 Elastic scattering 8928 1451 130 Covariances were given only to P1 components. 8928 1451 131 8928 1451 132 8928 1451 133 MF=35 Covariances for Energy Distributions 8928 1451 134 MT=18 Fission spectra 8928 1451 135 Estimated with CCONE and KALMAN codes. 8928 1451 136 8928 1451 137 8928 1451 138 ***************************************************************** 8928 1451 139 Calculation with CCONE code 8928 1451 140 ***************************************************************** 8928 1451 141 8928 1451 142 Models and parameters used in the CCONE/6/ calculation 8928 1451 143 1) Coupled channel optical model 8928 1451 144 Levels in the rotational band were included. Optical model 8928 1451 145 potential and coupled levels are shown in Table 1. 8928 1451 146 8928 1451 147 2) Two-component exciton model/10/ 8928 1451 148 * Global parametrization of Koning-Duijvestijn/11/ 8928 1451 149 was used. 8928 1451 150 * Gamma emission channel/12/ was added to simulate direct 8928 1451 151 and semi-direct capture reaction. 8928 1451 152 8928 1451 153 3) Hauser-Feshbach statistical model 8928 1451 154 * Moldauer width fluctuation correction/13/ was included. 8928 1451 155 * Neutron, gamma and fission decay channel were included. 8928 1451 156 * Transmission coefficients of neutrons were taken from 8928 1451 157 coupled channel calculation in Table 1. 8928 1451 158 * The level scheme of the target is shown in Table 2. 8928 1451 159 * Level density formula of constant temperature and Fermi-gas 8928 1451 160 model were used with shell energy correction and collective 8928 1451 161 enhancement factor. Parameters are shown in Table 3. 8928 1451 162 * Fission channel: 8928 1451 163 Double humped fission barriers were assumed. 8928 1451 164 Fission barrier penetrabilities were calculated with 8928 1451 165 Hill-Wheler formula/14/. Fission barrier parameters were 8928 1451 166 shown in Table 4. Transition state model was used and 8928 1451 167 continuum levels are assumed above the saddles. The level 8928 1451 168 density parameters for inner and outer saddles are shown in 8928 1451 169 Tables 5 and 6, respectively. 8928 1451 170 * Gamma-ray strength function of Kopecky et al/15/,/16/ 8928 1451 171 was used. The prameters are shown in Table 7. 8928 1451 172 8928 1451 173 8928 1451 174 ------------------------------------------------------------------8928 1451 175 Tables 8928 1451 176 ------------------------------------------------------------------8928 1451 177 8928 1451 178 Table 1. Coupled channel calculation 8928 1451 179 -------------------------------------------------- 8928 1451 180 * rigid rotor model was applied 8928 1451 181 * coupled levels = 0,2,4,7,9 (see Table 2) 8928 1451 182 * optical potential parameters /7/ 8928 1451 183 Volume: 8928 1451 184 V_0 = 49.97 MeV 8928 1451 185 lambda_HF = 0.01004 1/MeV 8928 1451 186 C_viso = 15.9 MeV 8928 1451 187 A_v = 12.04 MeV 8928 1451 188 B_v = 81.36 MeV 8928 1451 189 E_a = 385 MeV 8928 1451 190 r_v = 1.2568 fm 8928 1451 191 a_v = 0.633 fm 8928 1451 192 Surface: 8928 1451 193 W_0 = 17.2 MeV 8928 1451 194 B_s = 11.19 MeV 8928 1451 195 C_s = 0.01361 1/MeV 8928 1451 196 C_wiso = 23.5 MeV 8928 1451 197 r_s = 1.1803 fm 8928 1451 198 a_s = 0.601 fm 8928 1451 199 Spin-orbit: 8928 1451 200 V_so = 5.75 MeV 8928 1451 201 lambda_so = 0.005 1/MeV 8928 1451 202 W_so = -3.1 MeV 8928 1451 203 B_so = 160 MeV 8928 1451 204 r_so = 1.1214 fm 8928 1451 205 a_so = 0.59 fm 8928 1451 206 Coulomb: 8928 1451 207 C_coul = 1.3 8928 1451 208 r_c = 1.2452 fm 8928 1451 209 a_c = 0.545 fm 8928 1451 210 Deformation: 8928 1451 211 beta_2 = 0.213 8928 1451 212 beta_4 = 0.066 8928 1451 213 beta_6 = 0.0015 8928 1451 214 8928 1451 215 * Calculated strength function 8928 1451 216 S0= 1.04e-4 S1= 1.79e-4 R'= 10.00 fm (En=1 keV) 8928 1451 217 -------------------------------------------------- 8928 1451 218 8928 1451 219 Table 2. Level Scheme of Ac-226 8928 1451 220 ------------------- 8928 1451 221 No. Ex(MeV) J PI 8928 1451 222 ------------------- 8928 1451 223 0 0.00000 1 - * 8928 1451 224 1 0.00510 2 + 8928 1451 225 2 0.01880 2 - * 8928 1451 226 3 0.03330 5 - 8928 1451 227 4 0.04500 3 - * 8928 1451 228 5 0.05830 3 + 8928 1451 229 6 0.07030 3 - 8928 1451 230 7 0.07770 4 - * 8928 1451 231 ------------------- 8928 1451 232 *) Coupled levels in CC calculation 8928 1451 233 8928 1451 234 Table 3. Level density parameters 8928 1451 235 -------------------------------------------------------- 8928 1451 236 Nuclide a* Pair Eshell T E0 Ematch 8928 1451 237 1/MeV MeV MeV MeV MeV MeV 8928 1451 238 -------------------------------------------------------- 8928 1451 239 Ac-227 17.6369 0.7965 3.3377 0.4083 -1.1126 3.3578 8928 1451 240 Ac-226 17.5702 0.0000 3.0355 0.3357 -1.1051 1.5780 8928 1451 241 Ac-225 17.5034 0.8000 2.9322 0.4278 -1.2611 3.5537 8928 1451 242 Ac-224 17.4367 0.0000 2.4959 0.3776 -1.4315 1.9979 8928 1451 243 Ac-223 17.3698 0.8036 2.3884 0.4470 -1.3815 3.7226 8928 1451 244 -------------------------------------------------------- 8928 1451 245 8928 1451 246 Table 4. Fission barrier parameters 8928 1451 247 ---------------------------------------- 8928 1451 248 Nuclide V_A hw_A V_B hw_B 8928 1451 249 MeV MeV MeV MeV 8928 1451 250 ---------------------------------------- 8928 1451 251 Ac-227 7.000 0.800 7.100 0.930 8928 1451 252 Ac-226 7.000 0.800 7.100 0.900 8928 1451 253 Ac-225 7.000 0.800 7.100 0.930 8928 1451 254 Ac-224 7.000 0.800 7.100 0.900 8928 1451 255 Ac-223 7.000 0.800 7.100 0.930 8928 1451 256 ---------------------------------------- 8928 1451 257 8928 1451 258 Table 5. Level density above inner saddle 8928 1451 259 -------------------------------------------------------- 8928 1451 260 Nuclide a* Pair Eshell T E0 Ematch 8928 1451 261 1/MeV MeV MeV MeV MeV MeV 8928 1451 262 -------------------------------------------------------- 8928 1451 263 Ac-227 19.4006 0.9292 2.6000 0.3387 -1.4940 2.9292 8928 1451 264 Ac-226 18.4487 0.0000 2.6000 0.3484 -2.4548 2.0000 8928 1451 265 Ac-225 18.3786 0.9333 2.6000 0.3491 -1.5215 2.9333 8928 1451 266 Ac-224 18.3085 0.0000 2.6000 0.3498 -2.4549 2.0000 8928 1451 267 Ac-223 18.2383 0.9375 2.6000 0.3506 -1.5174 2.9375 8928 1451 268 -------------------------------------------------------- 8928 1451 269 8928 1451 270 Table 6. Level density above outer saddle 8928 1451 271 -------------------------------------------------------- 8928 1451 272 Nuclide a* Pair Eshell T E0 Ematch 8928 1451 273 1/MeV MeV MeV MeV MeV MeV 8928 1451 274 -------------------------------------------------------- 8928 1451 275 Ac-227 19.4006 0.9292 -0.4000 0.3875 -0.7697 2.9292 8928 1451 276 Ac-226 18.4487 0.0000 -0.4400 0.3999 -1.7104 2.0000 8928 1451 277 Ac-225 18.3786 0.9333 -0.4800 0.4014 -0.7766 2.9333 8928 1451 278 Ac-224 18.3085 0.0000 -0.5200 0.4028 -1.7094 2.0000 8928 1451 279 Ac-223 18.2383 0.9375 -0.5600 0.4043 -0.7713 2.9375 8928 1451 280 -------------------------------------------------------- 8928 1451 281 8928 1451 282 Table 7. Gamma-ray strength function for Ac-227 8928 1451 283 -------------------------------------------------------- 8928 1451 284 K0 = 1.503 E0 = 4.500 (MeV) 8928 1451 285 * E1: ER = 11.03 (MeV) EG = 2.71 (MeV) SIG = 302.00 (mb) 8928 1451 286 ER = 13.87 (MeV) EG = 4.77 (MeV) SIG = 449.00 (mb) 8928 1451 287 * M1: ER = 6.72 (MeV) EG = 4.00 (MeV) SIG = 2.82 (mb) 8928 1451 288 * E2: ER = 10.33 (MeV) EG = 3.39 (MeV) SIG = 6.14 (mb) 8928 1451 289 -------------------------------------------------------- 8928 1451 290 8928 1451 291 8928 1451 292 References 8928 1451 293 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 8928 1451 294 2) R.J.Tuttle: INDC(NDS)-107/G+Special, p.29 (1979). 8928 1451 295 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 8928 1451 296 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 8928 1451 297 5) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 8928 1451 298 6) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 8928 1451 299 7) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 8928 1451 300 8) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 8928 1451 301 9) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 8928 1451 302 Japanese. 8928 1451 303 10) C.Kalbach: Phys. Rev. C33, 818 (1986). 8928 1451 304 11) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 8928 1451 305 12) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 8928 1451 306 13) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 8928 1451 307 14) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 8928 1451 308 15) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 8928 1451 309 16) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 8928 1451 310 8928 1451 311 1 451 325 18928 1451 312 2 151 4 18928 1451 313 3 4 29 18928 1451 314 3 16 13 18928 1451 315 3 17 9 18928 1451 316 3 18 133 18928 1451 317 3 37 5 18928 1451 318 3 102 153 18928 1451 319 8 4 2 18928 1451 320 8 16 2 18928 1451 321 8 17 2 18928 1451 322 8 18 2 18928 1451 323 8 37 2 18928 1451 324 8 102 2 18928 1451 325 8928 1 099999 8928 0 0 0 8.922600+4 2.240840+2 0 0 1 08928 2151 1 8.922600+4 1.000000+0 0 0 1 08928 2151 2 1.000000-5 3.000000-1 0 0 0 08928 2151 3 1.000000+0 9.998000-1 0 0 0 08928 2151 4 8928 2 099999 8928 0 0 0 8.922600+4 2.240840+2 0 0 0 08928 3 4 1 0.000000+0-5.100000+3 0 0 1 788928 3 4 2 78 2 8928 3 4 3 5.122760+3 0.000000+0 7.000000+3 2.109620-2 1.000000+4 4.304330-28928 3 4 4 1.888390+4 9.712320-2 2.000000+4 1.575028-1 3.000000+4 2.681240-18928 3 4 5 3.344860+4 2.885940-1 4.520080+4 3.470725-1 5.000000+4 3.719655-18928 3 4 6 5.856020+4 4.102126-1 7.000000+4 4.864231-1 7.061370+4 4.893291-18928 3 4 7 7.804670+4 5.276941-1 1.000000+5 6.472289-1 1.109840+5 6.812312-18928 3 4 8 1.200000+5 7.091593-1 1.400000+5 7.730702-1 1.700000+5 8.808402-18928 3 4 9 2.000000+5 1.164234+0 2.500000+5 1.228670+0 3.000000+5 1.597422+08928 3 4 10 4.000000+5 1.813486+0 5.000000+5 2.125242+0 6.000000+5 2.254295+08928 3 4 11 7.000000+5 2.428315+0 8.000000+5 2.525424+0 9.000000+5 2.632759+08928 3 4 12 1.000000+6 2.751571+0 1.100000+6 2.847413+0 1.200000+6 2.939940+08928 3 4 13 1.300000+6 3.030504+0 1.400000+6 3.114260+0 1.500000+6 3.194853+08928 3 4 14 1.600000+6 3.268515+0 1.700000+6 3.334735+0 1.800000+6 3.394754+08928 3 4 15 1.900000+6 3.444371+0 2.000000+6 3.488618+0 2.100000+6 3.520870+08928 3 4 16 2.200000+6 3.548601+0 2.400000+6 3.585826+0 2.600000+6 3.603466+08928 3 4 17 2.800000+6 3.604832+0 3.000000+6 3.598212+0 3.500000+6 3.552733+08928 3 4 18 4.000000+6 3.499952+0 4.500000+6 3.417771+0 5.000000+6 3.362685+08928 3 4 19 5.500000+6 3.286478+0 6.000000+6 2.925462+0 6.500000+6 2.278927+08928 3 4 20 7.000000+6 1.732697+0 7.500000+6 1.329935+0 8.000000+6 1.059336+08928 3 4 21 8.500000+6 8.758008-1 9.000000+6 7.539384-1 9.500000+6 6.678853-18928 3 4 22 1.000000+7 6.057322-1 1.050000+7 5.634035-1 1.100000+7 5.228509-18928 3 4 23 1.150000+7 4.944814-1 1.200000+7 4.696719-1 1.250000+7 4.479075-18928 3 4 24 1.300000+7 4.279681-1 1.350000+7 4.136827-1 1.400000+7 3.960761-18928 3 4 25 1.450000+7 3.833595-1 1.500000+7 3.708791-1 1.550000+7 3.554433-18928 3 4 26 1.600000+7 3.439853-1 1.650000+7 3.332197-1 1.700000+7 3.225848-18928 3 4 27 1.750000+7 3.126870-1 1.800000+7 3.027421-1 1.850000+7 2.935007-18928 3 4 28 1.900000+7 2.883091-1 1.950000+7 2.796411-1 2.000000+7 2.710721-18928 3 4 29 8928 3 099999 8.922600+4 2.240840+2 0 0 0 08928 3 16 1 -5.399320+6-5.399320+6 0 0 1 308928 3 16 2 30 2 8928 3 16 3 5.423420+6 0.000000+0 6.000000+6 3.208890-1 6.500000+6 9.235900-18928 3 16 4 7.000000+6 1.453870+0 7.500000+6 1.831570+0 8.000000+6 2.087980+08928 3 16 5 8.500000+6 2.243490+0 9.000000+6 2.347160+0 9.500000+6 2.407320+08928 3 16 6 1.000000+7 2.449490+0 1.050000+7 2.469590+0 1.100000+7 2.490880+08928 3 16 7 1.150000+7 2.501520+0 1.200000+7 2.509110+0 1.250000+7 2.515980+08928 3 16 8 1.300000+7 2.499200+0 1.350000+7 2.410580+0 1.400000+7 2.251890+08928 3 16 9 1.450000+7 2.033420+0 1.500000+7 1.782580+0 1.550000+7 1.567920+08928 3 16 10 1.600000+7 1.333600+0 1.650000+7 1.157110+0 1.700000+7 1.006840+08928 3 16 11 1.750000+7 8.833380-1 1.800000+7 7.830930-1 1.850000+7 7.029070-18928 3 16 12 1.900000+7 6.339880-1 1.950000+7 5.812640-1 2.000000+7 5.515120-18928 3 16 13 8928 3 099999 8.922600+4 2.240840+2 0 0 0 08928 3 17 1 -1.206710+7-1.206710+7 0 0 1 178928 3 17 2 17 2 8928 3 17 3 1.212100+7 0.000000+0 1.250000+7 3.712430-4 1.300000+7 2.076200-28928 3 17 4 1.350000+7 1.088350-1 1.400000+7 2.676620-1 1.450000+7 4.834920-18928 3 17 5 1.500000+7 7.310930-1 1.550000+7 9.462490-1 1.600000+7 1.180120+08928 3 17 6 1.650000+7 1.355760+0 1.700000+7 1.505160+0 1.750000+7 1.629190+08928 3 17 7 1.800000+7 1.729760+0 1.850000+7 1.810760+0 1.900000+7 1.875260+08928 3 17 8 1.950000+7 1.923030+0 2.000000+7 1.931080+0 8928 3 17 9 8928 3 099999 8.922600+4 2.240840+2 0 0 0 08928 3 18 1 1.810000+8 1.810000+8 0 0 1 3898928 3 18 2 389 2 8928 3 18 3 1.000000-5 1.008709+2 1.103037-5 9.604382+1 1.216691-5 9.144774+18928 3 18 4 1.342055-5 8.707158+1 1.480336-5 8.290481+1 1.632865-5 7.893740+18928 3 18 5 1.801111-5 7.515983+1 1.986691-5 7.156300+1 2.191394-5 6.813826+18928 3 18 6 2.417189-5 6.487739+1 2.666248-5 6.177253+1 2.940971-5 5.881623+18928 3 18 7 3.243999-5 5.600137+1 3.578251-5 5.332119+1 3.946943-5 5.076923+18928 3 18 8 4.353624-5 4.833938+1 4.802208-5 4.602577+1 5.297013-5 4.382286+18928 3 18 9 5.842801-5 4.172534+1 6.444825-5 3.972817+1 7.108881-5 3.782655+18928 3 18 10 7.841358-5 3.601591+1 8.649308-5 3.429189+1 9.540506-5 3.265035+18928 3 18 11 1.052353-4 3.108735+1 1.160784-4 2.959913+1 1.280388-4 2.818211+18928 3 18 12 1.412315-4 2.683289+1 1.557836-4 2.554822+1 1.718351-4 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