JENDL-5 (Neutron sublibrary (activation cs)) Cf-254 0 0 0 0 9.825400+4 2.519050+2 0 0 6 19867 1451 1 0.000000+0 1.000000+0 0 0 0 69867 1451 2 1.000000+0 2.000000+7 0 0 10 59867 1451 3 2.936000+2 0.000000+0 4 0 309 149867 1451 4 98-Cf-254 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9867 1451 5 DIST-DEC21 20100304 9867 1451 6 ----JENDL-5 MATERIAL 9867 9867 1451 7 -----INCIDENT NEUTRON DATA 9867 1451 8 ------ENDF-6 FORMAT 9867 1451 9 9867 1451 10 History 9867 1451 11 07-09 Theoretical calculation was performed with CCONE code. 9867 1451 12 Data were compiled as JENDL/AC-2008/1/. 9867 1451 13 10-02 Data of prompt gamma rays due to fission were given. 9867 1451 14 10-03 Covariance data were given. 9867 1451 15 21-11 revised by O.Iwamoto 9867 1451 16 (MF3/MT19-21,38) deleted 9867 1451 17 (MF8/MT16-18,37,102) JENDL/AD-2017 adopted 9867 1451 18 (MF8/MT4) added 9867 1451 19 9867 1451 20 9867 1451 21 MF=1 General information 9867 1451 22 MT=452 Number of Neutrons per fission 9867 1451 23 Sum of MT's=455 and 456. 9867 1451 24 9867 1451 25 MT=455 Delayed neutron data 9867 1451 26 (Same as JENDL-3.3) 9867 1451 27 Estimated from systematics by Tuttle/2/, Benedetti et al./3/ 9867 1451 28 and Waldo et al./4/ 9867 1451 29 9867 1451 30 MT=456 Number of prompt neutrons per fission 9867 1451 31 (Same as JENDL-3.3) 9867 1451 32 Estimated from Howerton's sytematics/5/. 9867 1451 33 9867 1451 34 9867 1451 35 MF= 2 Resonance parameters 9867 1451 36 MT=151 9867 1451 37 No resonance parameters are given. 9867 1451 38 9867 1451 39 9867 1451 40 Thermal cross sections and resonance integrals (at 300K) 9867 1451 41 ------------------------------------------------------- 9867 1451 42 0.0253 eV reson. integ.(*) 9867 1451 43 (barns) (barns) 9867 1451 44 ------------------------------------------------------- 9867 1451 45 total 17.26 9867 1451 46 elastic 10.72 9867 1451 47 fission 2.00 103 9867 1451 48 capture 4.50 37.2 9867 1451 49 ------------------------------------------------------- 9867 1451 50 (*) In the energy range from 0.5 eV to 10 MeV. 9867 1451 51 9867 1451 52 9867 1451 53 MF= 3 Neutron cross sections 9867 1451 54 Below 13 eV: 9867 1451 55 * Elastic scattering cross section is 10.7 b calculated from 9867 1451 56 scattering radius of 9.236 fm/6/. 9867 1451 57 * Fission cross section is in the 1/v shape, and 2 b at 9867 1451 58 0.0253 eV was estimated from systematics. 9867 1451 59 * Capture cross section is in the 1/v shape, and 4.5 b at 9867 1451 60 0.0253 eV which was measured by Lougheed et al./7/ 9867 1451 61 9867 1451 62 Above 13 eV: 9867 1451 63 Cross sections were calculated with CCONE code/6/. 9867 1451 64 9867 1451 65 MT= 1 Total cross section 9867 1451 66 The cross section was calculated with CC OMP of Soukhovitskii 9867 1451 67 et al./8/ 9867 1451 68 9867 1451 69 9867 1451 70 MF= 4 Angular distributions of secondary neutrons 9867 1451 71 MT=2 Elastic scattering 9867 1451 72 Calculated with CCONE code/6/. 9867 1451 73 9867 1451 74 MT=18 Fission 9867 1451 75 Isotropic distributions in the laboratory system were assumed.9867 1451 76 9867 1451 77 9867 1451 78 MF= 5 Energy distributions of secondary neutrons 9867 1451 79 MT=18 Prompt netrons 9867 1451 80 Calculated with CCONE code/6/. 9867 1451 81 9867 1451 82 9867 1451 83 MF= 6 Energy-angle distributions 9867 1451 84 Calculated with CCONE code/6/. 9867 1451 85 Distributions from fission (MT=18) are not included. 9867 1451 86 9867 1451 87 9867 1451 88 MF=12 Photon production multiplicities 9867 1451 89 MT=18 Fission 9867 1451 90 Calculated from the total energy released by the prompt 9867 1451 91 gamma-rays due to fission which was estimated from its 9867 1451 92 systematics, and the average energy of gamma-rays. 9867 1451 93 9867 1451 94 9867 1451 95 MF=14 Photon angular distributions 9867 1451 96 MT=18 Fission 9867 1451 97 Isotoropic distributions were assumed. 9867 1451 98 9867 1451 99 9867 1451 100 MF=15 Continuous photon energy spectra 9867 1451 101 MT=18 Fission 9867 1451 102 Experimental data measured by Verbinski et al./9/ for 9867 1451 103 Pu-239 thermal fission were adopted. 9867 1451 104 9867 1451 105 9867 1451 106 MF=31 Covariances of average number of neutrons per fission 9867 1451 107 MT=452 Number of neutrons per fission 9867 1451 108 Sum of covariances for MT=455 and MT=456. 9867 1451 109 9867 1451 110 MT=455 9867 1451 111 Error of 15% was assumed. 9867 1451 112 9867 1451 113 MT=456 9867 1451 114 Covariance was obtained by fitting a linear function to the 9867 1451 115 at 0.0 and 5.0 MeV with an uncertainty of 10%. 9867 1451 116 9867 1451 117 9867 1451 118 MF=33 Covariances of neutron cross sections 9867 1451 119 Covariances were given to all the cross sections by using 9867 1451 120 KALMAN code/10/ and the covariances of model parameters 9867 1451 121 used in the cross-section calculations. 9867 1451 122 9867 1451 123 For the following cross sections, standard deviations in the 9867 1451 124 energy region below 13 eV were assumed as follows: 9867 1451 125 9867 1451 126 Total 34 % 9867 1451 127 Elastic scattering 50 % 9867 1451 128 Fission 50 % 9867 1451 129 Capture 50 % 9867 1451 130 9867 1451 131 9867 1451 132 MF=34 Covariances for Angular Distributions 9867 1451 133 MT=2 Elastic scattering 9867 1451 134 Covariances were given only to P1 components. 9867 1451 135 9867 1451 136 9867 1451 137 MF=35 Covariances for Energy Distributions 9867 1451 138 MT=18 Fission spectra 9867 1451 139 Estimated with CCONE and KALMAN codes. 9867 1451 140 9867 1451 141 9867 1451 142 ***************************************************************** 9867 1451 143 Calculation with CCONE code 9867 1451 144 ***************************************************************** 9867 1451 145 9867 1451 146 Models and parameters used in the CCONE/6/ calculation 9867 1451 147 1) Coupled channel optical model 9867 1451 148 Levels in the rotational band were included. Optical model 9867 1451 149 potential and coupled levels are shown in Table 1. 9867 1451 150 9867 1451 151 2) Two-component exciton model/11/ 9867 1451 152 * Global parametrization of Koning-Duijvestijn/12/ 9867 1451 153 was used. 9867 1451 154 * Gamma emission channel/13/ was added to simulate direct 9867 1451 155 and semi-direct capture reaction. 9867 1451 156 9867 1451 157 3) Hauser-Feshbach statistical model 9867 1451 158 * Moldauer width fluctuation correction/14/ was included. 9867 1451 159 * Neutron, gamma and fission decay channel were included. 9867 1451 160 * Transmission coefficients of neutrons were taken from 9867 1451 161 coupled channel calculation in Table 1. 9867 1451 162 * The level scheme of the target is shown in Table 2. 9867 1451 163 * Level density formula of constant temperature and Fermi-gas 9867 1451 164 model were used with shell energy correction and collective 9867 1451 165 enhancement factor. Parameters are shown in Table 3. 9867 1451 166 * Fission channel: 9867 1451 167 Double humped fission barriers were assumed. 9867 1451 168 Fission barrier penetrabilities were calculated with 9867 1451 169 Hill-Wheler formula/15/. Fission barrier parameters were 9867 1451 170 shown in Table 4. Transition state model was used and 9867 1451 171 continuum levels are assumed above the saddles. The level 9867 1451 172 density parameters for inner and outer saddles are shown in 9867 1451 173 Tables 5 and 6, respectively. 9867 1451 174 * Gamma-ray strength function of Kopecky et al/16/,/17/ 9867 1451 175 was used. The prameters are shown in Table 7. 9867 1451 176 9867 1451 177 9867 1451 178 ------------------------------------------------------------------9867 1451 179 Tables 9867 1451 180 ------------------------------------------------------------------9867 1451 181 9867 1451 182 Table 1. Coupled channel calculation 9867 1451 183 -------------------------------------------------- 9867 1451 184 * rigid rotor model was applied 9867 1451 185 * coupled levels = 0,1,2,3,4 (see Table 2) 9867 1451 186 * optical potential parameters /8/ 9867 1451 187 Volume: 9867 1451 188 V_0 = 49.97 MeV 9867 1451 189 lambda_HF = 0.01004 1/MeV 9867 1451 190 C_viso = 15.9 MeV 9867 1451 191 A_v = 12.04 MeV 9867 1451 192 B_v = 81.36 MeV 9867 1451 193 E_a = 385 MeV 9867 1451 194 r_v = 1.2568 fm 9867 1451 195 a_v = 0.633 fm 9867 1451 196 Surface: 9867 1451 197 W_0 = 17.2 MeV 9867 1451 198 B_s = 11.19 MeV 9867 1451 199 C_s = 0.01361 1/MeV 9867 1451 200 C_wiso = 23.5 MeV 9867 1451 201 r_s = 1.1803 fm 9867 1451 202 a_s = 0.601 fm 9867 1451 203 Spin-orbit: 9867 1451 204 V_so = 5.75 MeV 9867 1451 205 lambda_so = 0.005 1/MeV 9867 1451 206 W_so = -3.1 MeV 9867 1451 207 B_so = 160 MeV 9867 1451 208 r_so = 1.1214 fm 9867 1451 209 a_so = 0.59 fm 9867 1451 210 Coulomb: 9867 1451 211 C_coul = 1.3 9867 1451 212 r_c = 1.2452 fm 9867 1451 213 a_c = 0.545 fm 9867 1451 214 Deformation: 9867 1451 215 beta_2 = 0.213 9867 1451 216 beta_4 = 0.066 9867 1451 217 beta_6 = 0.0015 9867 1451 218 9867 1451 219 * Calculated strength function 9867 1451 220 S0= 1.44e-4 S1= 2.89e-4 R'= 9.24 fm (En=1 keV) 9867 1451 221 -------------------------------------------------- 9867 1451 222 9867 1451 223 Table 2. Level Scheme of Cf-254 9867 1451 224 ------------------- 9867 1451 225 No. Ex(MeV) J PI 9867 1451 226 ------------------- 9867 1451 227 0 0.00000 0 + * 9867 1451 228 1 0.04572 2 + * 9867 1451 229 2 0.15173 4 + * 9867 1451 230 3 0.31920 6 + * 9867 1451 231 4 0.54720 8 + * 9867 1451 232 ------------------- 9867 1451 233 *) Coupled levels in CC calculation 9867 1451 234 9867 1451 235 Table 3. Level density parameters 9867 1451 236 -------------------------------------------------------- 9867 1451 237 Nuclide a* Pair Eshell T E0 Ematch 9867 1451 238 1/MeV MeV MeV MeV MeV MeV 9867 1451 239 -------------------------------------------------------- 9867 1451 240 Cf-255 19.4922 0.7515 2.7279 0.3524 -0.7149 2.7515 9867 1451 241 Cf-254 19.4263 1.5059 2.4305 0.3644 -0.0499 3.6204 9867 1451 242 Cf-253 19.3604 0.7544 2.0655 0.3368 -0.4669 2.4564 9867 1451 243 Cf-252 19.2945 1.5119 1.7395 0.3655 0.0444 3.5280 9867 1451 244 Cf-251 19.2285 0.7574 1.2773 0.3926 -0.9361 3.0632 9867 1451 245 -------------------------------------------------------- 9867 1451 246 9867 1451 247 Table 4. Fission barrier parameters 9867 1451 248 ---------------------------------------- 9867 1451 249 Nuclide V_A hw_A V_B hw_B 9867 1451 250 MeV MeV MeV MeV 9867 1451 251 ---------------------------------------- 9867 1451 252 Cf-255 5.600 1.000 4.600 0.800 9867 1451 253 Cf-254 6.200 1.040 5.400 0.600 9867 1451 254 Cf-253 5.600 1.000 4.600 0.800 9867 1451 255 Cf-252 6.000 1.040 5.000 0.800 9867 1451 256 Cf-251 6.200 0.800 5.000 0.600 9867 1451 257 ---------------------------------------- 9867 1451 258 9867 1451 259 Table 5. Level density above inner saddle 9867 1451 260 -------------------------------------------------------- 9867 1451 261 Nuclide a* Pair Eshell T E0 Ematch 9867 1451 262 1/MeV MeV MeV MeV MeV MeV 9867 1451 263 -------------------------------------------------------- 9867 1451 264 Cf-255 21.8312 0.8767 2.5000 0.3394 -1.8575 3.1767 9867 1451 265 Cf-254 21.7575 1.7569 2.5000 0.3191 -0.6561 3.7569 9867 1451 266 Cf-253 21.6837 0.8802 2.5000 0.3407 -1.8541 3.1802 9867 1451 267 Cf-252 21.6098 1.7638 2.5000 0.3202 -0.6492 3.7638 9867 1451 268 Cf-251 21.5360 0.8837 2.5000 0.3208 -1.5294 2.8837 9867 1451 269 -------------------------------------------------------- 9867 1451 270 9867 1451 271 Table 6. Level density above outer saddle 9867 1451 272 -------------------------------------------------------- 9867 1451 273 Nuclide a* Pair Eshell T E0 Ematch 9867 1451 274 1/MeV MeV MeV MeV MeV MeV 9867 1451 275 -------------------------------------------------------- 9867 1451 276 Cf-255 21.8312 0.8767 1.1600 0.3445 -0.8360 2.8767 9867 1451 277 Cf-254 21.7575 1.7569 1.1200 0.3455 0.0447 3.7569 9867 1451 278 Cf-253 21.6837 0.8802 1.0800 0.3466 -0.8314 2.8802 9867 1451 279 Cf-252 21.6098 1.7638 1.0400 0.3477 0.0528 3.7638 9867 1451 280 Cf-251 21.5360 0.8837 1.0000 0.3488 -0.8268 2.8837 9867 1451 281 -------------------------------------------------------- 9867 1451 282 9867 1451 283 Table 7. Gamma-ray strength function for Cf-255 9867 1451 284 -------------------------------------------------------- 9867 1451 285 K0 = 1.500 E0 = 4.500 (MeV) 9867 1451 286 * E1: ER = 11.37 (MeV) EG = 2.70 (MeV) SIG = 260.65 (mb) 9867 1451 287 ER = 14.17 (MeV) EG = 4.11 (MeV) SIG = 521.30 (mb) 9867 1451 288 * M1: ER = 6.47 (MeV) EG = 4.00 (MeV) SIG = 1.87 (mb) 9867 1451 289 * E2: ER = 9.93 (MeV) EG = 3.05 (MeV) SIG = 7.35 (mb) 9867 1451 290 -------------------------------------------------------- 9867 1451 291 9867 1451 292 9867 1451 293 References 9867 1451 294 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9867 1451 295 2) R.J.Tuttld: INDC(NDS)-107/G+Special, p.29 (1979). 9867 1451 296 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 9867 1451 297 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 9867 1451 298 5) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9867 1451 299 6) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9867 1451 300 7) R.W.Lougheed et al.: J. Inorg. Nucl. Chem., 43, 2239(1981). 9867 1451 301 8) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9867 1451 302 9) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9867 1451 303 10) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9867 1451 304 Japanese. 9867 1451 305 11) C.Kalbach: Phys. Rev. C33, 818 (1986). 9867 1451 306 12) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9867 1451 307 13) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9867 1451 308 14) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9867 1451 309 15) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9867 1451 310 16) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9867 1451 311 17) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9867 1451 312 9867 1451 313 1 451 327 19867 1451 314 2 151 4 19867 1451 315 3 4 27 19867 1451 316 3 16 13 19867 1451 317 3 17 10 19867 1451 318 3 18 159 19867 1451 319 3 37 6 19867 1451 320 3 102 178 19867 1451 321 8 4 2 19867 1451 322 8 16 2 19867 1451 323 8 17 2 19867 1451 324 8 18 2 19867 1451 325 8 37 2 19867 1451 326 8 102 2 19867 1451 327 9867 1 099999 9867 0 0 0 9.825400+4 2.519050+2 0 0 1 09867 2151 1 9.825400+4 1.000000+0 0 0 1 09867 2151 2 1.000000-5 1.300000+1 0 0 0 09867 2151 3 0.000000+0 8.096550-1 0 0 0 09867 2151 4 9867 2 099999 9867 0 0 0 9.825400+4 2.519050+2 0 0 0 09867 3 4 1 0.000000+0-4.572000+4 0 0 1 709867 3 4 2 70 2 9867 3 4 3 4.590150+4 0.000000+0 5.000000+4 6.840200-2 7.000000+4 3.652670-19867 3 4 4 1.000000+5 6.654810-1 1.108750+5 7.368640-1 1.200000+5 7.967650-19867 3 4 5 1.400000+5 9.065267-1 1.523320+5 9.661033-1 1.700000+5 1.044352+09867 3 4 6 2.000000+5 1.174562+0 2.500000+5 1.303745+0 3.000000+5 1.411795+09867 3 4 7 3.204670+5 1.425948+0 4.000000+5 1.472711+0 5.000000+5 1.543064+09867 3 4 8 5.493720+5 1.537510+0 6.000000+5 1.522894+0 7.000000+5 1.521414+09867 3 4 9 8.000000+5 1.526905+0 9.000000+5 1.541670+0 1.000000+6 1.567162+09867 3 4 10 1.100000+6 1.591383+0 1.200000+6 1.615368+0 1.300000+6 1.635109+09867 3 4 11 1.400000+6 1.658420+0 1.500000+6 1.671462+0 1.600000+6 1.686006+09867 3 4 12 1.700000+6 1.688226+0 1.800000+6 1.690561+0 1.900000+6 1.682024+09867 3 4 13 2.000000+6 1.673270+0 2.100000+6 1.656932+0 2.300000+6 1.623481+09867 3 4 14 2.500000+6 1.584373+0 2.700000+6 1.546232+0 3.000000+6 1.493031+09867 3 4 15 3.500000+6 1.446197+0 4.000000+6 1.430027+0 4.500000+6 1.460212+09867 3 4 16 5.000000+6 1.496185+0 5.500000+6 1.520078+0 6.000000+6 1.451330+09867 3 4 17 6.500000+6 1.266612+0 7.000000+6 1.062120+0 7.500000+6 8.979247-19867 3 4 18 8.000000+6 7.866843-1 8.500000+6 7.094464-1 9.000000+6 6.532907-19867 3 4 19 9.500000+6 6.100730-1 1.000000+7 5.761963-1 1.050000+7 5.478460-19867 3 4 20 1.100000+7 5.226831-1 1.150000+7 5.010362-1 1.200000+7 4.793942-19867 3 4 21 1.250000+7 4.604395-1 1.300000+7 4.417794-1 1.350000+7 4.257129-19867 3 4 22 1.400000+7 4.086481-1 1.450000+7 3.933810-1 1.500000+7 3.790073-19867 3 4 23 1.550000+7 3.662189-1 1.600000+7 3.528061-1 1.650000+7 3.414525-19867 3 4 24 1.700000+7 3.302948-1 1.750000+7 3.202902-1 1.800000+7 3.104546-19867 3 4 25 1.850000+7 3.016612-1 1.900000+7 2.928568-1 1.950000+7 2.856497-19867 3 4 26 2.000000+7 2.777583-1 9867 3 4 27 9867 3 099999 9.825400+4 2.519050+2 0 0 0 09867 3 16 1 -6.031560+6-6.031560+6 0 0 1 299867 3 16 2 29 2 9867 3 16 3 6.055510+6 0.000000+0 6.500000+6 9.507290-2 7.000000+6 3.340750-19867 3 16 4 7.500000+6 5.485260-1 8.000000+6 7.152780-1 8.500000+6 8.145260-19867 3 16 5 9.000000+6 9.024020-1 9.500000+6 9.615380-1 1.000000+7 1.005480+09867 3 16 6 1.050000+7 1.030340+0 1.100000+7 1.036910+0 1.150000+7 9.978030-19867 3 16 7 1.200000+7 9.116680-1 1.250000+7 7.956290-1 1.300000+7 6.699760-19867 3 16 8 1.350000+7 5.588530-1 1.400000+7 4.750310-1 1.450000+7 4.144520-19867 3 16 9 1.500000+7 3.630890-1 1.550000+7 3.285260-1 1.600000+7 3.067620-19867 3 16 10 1.650000+7 2.873460-1 1.700000+7 2.715450-1 1.750000+7 2.583360-19867 3 16 11 1.800000+7 2.472330-1 1.850000+7 2.381720-1 1.900000+7 2.292560-19867 3 16 12 1.950000+7 2.186380-1 2.000000+7 2.111350-1 9867 3 16 13 9867 3 099999 9.825400+4 2.519050+2 0 0 0 09867 3 17 1 -1.083580+7-1.083580+7 0 0 1 199867 3 17 2 19 2 9867 3 17 3 1.087890+7 0.000000+0 1.150000+7 1.783090-3 1.200000+7 1.353670-29867 3 17 4 1.250000+7 3.413280-2 1.300000+7 5.540250-2 1.350000+7 7.335160-29867 3 17 5 1.400000+7 8.734500-2 1.450000+7 9.844470-2 1.500000+7 1.083100-19867 3 17 6 1.550000+7 1.103200-1 1.600000+7 1.176010-1 1.650000+7 1.208820-19867 3 17 7 1.700000+7 1.247280-1 1.750000+7 1.288380-1 1.800000+7 1.314680-19867 3 17 8 1.850000+7 1.304760-1 1.900000+7 1.253540-1 1.950000+7 1.202000-19867 3 17 9 2.000000+7 1.118390-1 9867 3 17 10 9867 3 099999 9.825400+4 2.519050+2 0 0 0 09867 3 18 1 2.199000+8 2.199000+8 0 0 1 4679867 3 18 2 467 2 9867 3 18 3 1.000000-5 1.001853+2 1.103037-5 9.539182+1 1.216691-5 9.082773+19867 3 18 4 1.342055-5 8.648205+1 1.480336-5 8.234434+1 1.632865-5 7.840465+19867 3 18 5 1.801111-5 7.465350+1 1.986691-5 7.108187+1 2.191394-5 6.768117+19867 3 18 6 2.417189-5 6.444323+1 2.666248-5 6.136025+1 2.940971-5 5.842482+19867 3 18 7 3.243999-5 5.562988+1 3.578251-5 5.296872+1 3.946943-5 5.043491+19867 3 18 8 4.353624-5 4.802239+1 4.802208-5 4.572533+1 5.297013-5 4.353821+19867 3 18 9 5.842801-5 4.145578+1 6.444825-5 3.947302+1 7.108881-5 3.758517+19867 3 18 10 7.841358-5 3.578767+1 8.649308-5 3.407621+1 9.540506-5 3.244667+19867 3 18 11 1.052353-4 3.089512+1 1.160784-4 2.941783+1 1.280388-4 2.801124+19867 3 18 12 1.412315-4 2.667197+1 1.557836-4 2.539679+1 1.718351-4 2.418264+19867 3 18 13 1.895404-4 2.302658+1 2.090701-4 2.192584+1 2.306120-4 2.087776+19867 3 18 14 2.543736-4 1.987983+1 2.805835-4 1.892963+1 3.094939-4 1.802488+19867 3 18 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