JENDL-5 (Neutron sublibrary (activation cs)) Cm-240 0 0 0 0 9.624000+4 2.379930+2 0 0 6 19625 1451 1 0.000000+0 1.000000+0 0 0 0 69625 1451 2 1.000000+0 2.000000+7 0 0 10 59625 1451 3 2.936000+2 0.000000+0 4 0 311 129625 1451 4 96-Cm-240 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9625 1451 5 DIST-DEC21 20100304 9625 1451 6 ----JENDL-5 MATERIAL 9625 9625 1451 7 -----INCIDENT NEUTRON DATA 9625 1451 8 ------ENDF-6 FORMAT 9625 1451 9 9625 1451 10 History 9625 1451 11 07-08 Theoretical calculation was performed with CCONE code. 9625 1451 12 07-10 Theoretical calculation was performed with CCONE code. 9625 1451 13 Data were compiled as JENDL/AC-2008/1/. 9625 1451 14 10-02 Data of prompt gamma rays due to fission were given. 9625 1451 15 10-03 Covariance data were given. 9625 1451 16 9625 1451 17 21-11 revised by O.Iwamoto 9625 1451 18 (MF3/MT19-21,38) deleted 9625 1451 19 (MF8/MT4,16-18,102) added 9625 1451 20 9625 1451 21 MF=1 General information 9625 1451 22 MT=452 Number of Neutrons per fission 9625 1451 23 Sum of MT's=455 and 456. 9625 1451 24 9625 1451 25 MT=455 Delayed neutron data 9625 1451 26 (Same as JENDL-3.3) 9625 1451 27 Estimated from Tuttle's systematics /2/. 9625 1451 28 9625 1451 29 MT=456 Number of prompt neutrons per fission 9625 1451 30 (Same as JENDL-3.3) 9625 1451 31 Estimated from Howerton's sytematics /3/. 9625 1451 32 9625 1451 33 9625 1451 34 MF= 2 Resonance parameters 9625 1451 35 MT=151 9625 1451 36 No resonance parameters are given. 9625 1451 37 9625 1451 38 9625 1451 39 Thermal cross sections and resonance integrals (at 300K) 9625 1451 40 ------------------------------------------------------- 9625 1451 41 0.0253 eV reson. integ.(*) 9625 1451 42 (barns) (barns) 9625 1451 43 ------------------------------------------------------- 9625 1451 44 total 91.08 9625 1451 45 elastic 10.92 9625 1451 46 fission 30.01 188 9625 1451 47 capture 50.01 293 9625 1451 48 ------------------------------------------------------- 9625 1451 49 (*) In the energy range from 0.5 eV to 10 MeV. 9625 1451 50 9625 1451 51 9625 1451 52 MF= 3 Neutron cross sections 9625 1451 53 Below 3.2 eV: 9625 1451 54 * Elastic scattering cross section is 10.9 b calculated from 9625 1451 55 scattering radius of 9.29fm/4/. 9625 1451 56 * Capture cross section is in the 1/v shape, and 50 b at 9625 1451 57 0.0253 eV which was estimated from systematics. 9625 1451 58 * Fission cross section is in the 1/v shape, and 30 b at 9625 1451 59 0.0253 eV which was estimated by assuming that the cross- 9625 1451 60 section ratio of capture and fission was the same as that 9625 1451 61 at 1 eV calculated with CCONE code /4/. 9625 1451 62 9625 1451 63 Above 3.2 eV: 9625 1451 64 Cross sections were calculated with CCONE code/4/. 9625 1451 65 9625 1451 66 MT= 1 Total cross section 9625 1451 67 The cross section was calculated with CC OMP of Soukhovitskii 9625 1451 68 et al./5/. 9625 1451 69 9625 1451 70 MT=18 Fission cross section 9625 1451 71 The simulated (n,f) cross sections of Britt and Wilhelmy/6/ 9625 1451 72 were used to determine the parameters in the CCONE 9625 1451 73 calculation. 9625 1451 74 9625 1451 75 9625 1451 76 MF= 4 Angular distributions of secondary neutrons 9625 1451 77 MT=2 Elastic scattering 9625 1451 78 Calculated with CCONE code. 9625 1451 79 9625 1451 80 MT=18 Fission 9625 1451 81 Isotropic distributions in the laboratory system were assumed.9625 1451 82 9625 1451 83 9625 1451 84 MF= 5 Energy distributions of secondary neutrons 9625 1451 85 MT=18 Prompt neutrons 9625 1451 86 Calculated with CCONE code/4/. 9625 1451 87 9625 1451 88 9625 1451 89 MF= 6 Energy-angle distributions 9625 1451 90 Calculated with CCONE code. 9625 1451 91 Distributions from fission (MT=18) are not included. 9625 1451 92 9625 1451 93 9625 1451 94 MF=12 Photon production multiplicities 9625 1451 95 MT=18 Fission 9625 1451 96 Calculated from the total energy released by the prompt 9625 1451 97 gamma-rays due to fission which was estimated from its 9625 1451 98 systematics, and the average energy of gamma-rays. 9625 1451 99 9625 1451 100 9625 1451 101 MF=14 Photon angular distributions 9625 1451 102 MT=18 Fission 9625 1451 103 Isotoropic distributions were assumed. 9625 1451 104 9625 1451 105 9625 1451 106 MF=15 Continuous photon energy spectra 9625 1451 107 MT=18 Fission 9625 1451 108 Experimental data measured by Verbinski et al./7/ for 9625 1451 109 Pu-239 thermal fission were adopted. 9625 1451 110 9625 1451 111 9625 1451 112 MF=31 Covariances of average number of neutrons per fission 9625 1451 113 MT=452 Number of neutrons per fission 9625 1451 114 Sum of covariances for MT=455 and MT=456. 9625 1451 115 9625 1451 116 MT=455 9625 1451 117 Error of 15% was assumed. 9625 1451 118 9625 1451 119 MT=456 9625 1451 120 Covariance was obtained by fitting a linear function to the 9625 1451 121 at 0.0 and 5.0 MeV with an uncertainty of 5%. 9625 1451 122 9625 1451 123 9625 1451 124 MF=33 Covariances of neutron cross sections 9625 1451 125 Covariances were given to all the cross sections by using 9625 1451 126 KALMAN code/8/ and the covariances of model parameters 9625 1451 127 used in the cross-section calculations. 9625 1451 128 9625 1451 129 Covariances of the fission cross section were determined from 9625 1451 130 experimental data. 9625 1451 131 9625 1451 132 For the following cross sections, standard deviations in the 9625 1451 133 energy region below 3.2 eV were assumed as follows: 9625 1451 134 9625 1451 135 Total 33 % 9625 1451 136 Elastic scattering 50 % 9625 1451 137 Fission 50 % 9625 1451 138 Capture 50 % 9625 1451 139 9625 1451 140 9625 1451 141 MF=34 Covariances for Angular Distributions 9625 1451 142 MT=2 Elastic scattering 9625 1451 143 Covariances were given only to P1 components. 9625 1451 144 9625 1451 145 9625 1451 146 MF=35 Covariances for Energy Distributions 9625 1451 147 MT=18 Fission spectra 9625 1451 148 Estimated with CCONE and KALMAN codes. 9625 1451 149 9625 1451 150 9625 1451 151 ***************************************************************** 9625 1451 152 Calculation with CCONE code 9625 1451 153 ***************************************************************** 9625 1451 154 9625 1451 155 Models and parameters used in the CCONE/4/ calculation 9625 1451 156 1) Coupled channel optical model 9625 1451 157 Levels in the rotational band were included. Optical model 9625 1451 158 potential and coupled levels are shown in Table 1. 9625 1451 159 9625 1451 160 2) Two-component exciton model/9/ 9625 1451 161 * Global parametrization of Koning-Duijvestijn/10/ 9625 1451 162 was used. 9625 1451 163 * Gamma emission channel/11/ was added to simulate direct 9625 1451 164 and semi-direct capture reaction. 9625 1451 165 9625 1451 166 3) Hauser-Feshbach statistical model 9625 1451 167 * Moldauer width fluctuation correction/12/ was included. 9625 1451 168 * Neutron, gamma and fission decay channel were included. 9625 1451 169 * Transmission coefficients of neutrons were taken from 9625 1451 170 coupled channel calculation in Table 1. 9625 1451 171 * The level scheme of the target is shown in Table 2. 9625 1451 172 * Level density formula of constant temperature and Fermi-gas 9625 1451 173 model were used with shell energy correction and collective 9625 1451 174 enhancement factor. Parameters are shown in Table 3. 9625 1451 175 * Fission channel: 9625 1451 176 Double humped fission barriers were assumed. 9625 1451 177 Fission barrier penetrabilities were calculated with 9625 1451 178 Hill-Wheler formula/13/. Fission barrier parameters were 9625 1451 179 shown in Table 4. Transition state model was used and 9625 1451 180 continuum levels are assumed above the saddles. The level 9625 1451 181 density parameters for inner and outer saddles are shown in 9625 1451 182 Tables 5 and 6, respectively. 9625 1451 183 * Gamma-ray strength function of Kopecky et al/14/,/15/ 9625 1451 184 was used. The prameters are shown in Table 7. 9625 1451 185 9625 1451 186 9625 1451 187 ------------------------------------------------------------------9625 1451 188 Tables 9625 1451 189 ------------------------------------------------------------------9625 1451 190 9625 1451 191 Table 1. Coupled channel calculation 9625 1451 192 -------------------------------------------------- 9625 1451 193 * rigid rotor model was applied 9625 1451 194 * coupled levels = 0,1,2,3,4 (see Table 2) 9625 1451 195 * optical potential parameters /5/ 9625 1451 196 Volume: 9625 1451 197 V_0 = 49.97 MeV 9625 1451 198 lambda_HF = 0.01004 1/MeV 9625 1451 199 C_viso = 15.9 MeV 9625 1451 200 A_v = 12.04 MeV 9625 1451 201 B_v = 81.36 MeV 9625 1451 202 E_a = 385 MeV 9625 1451 203 r_v = 1.2568 fm 9625 1451 204 a_v = 0.633 fm 9625 1451 205 Surface: 9625 1451 206 W_0 = 17.2 MeV 9625 1451 207 B_s = 11.19 MeV 9625 1451 208 C_s = 0.01361 1/MeV 9625 1451 209 C_wiso = 23.5 MeV 9625 1451 210 r_s = 1.1803 fm 9625 1451 211 a_s = 0.601 fm 9625 1451 212 Spin-orbit: 9625 1451 213 V_so = 5.75 MeV 9625 1451 214 lambda_so = 0.005 1/MeV 9625 1451 215 W_so = -3.1 MeV 9625 1451 216 B_so = 160 MeV 9625 1451 217 r_so = 1.1214 fm 9625 1451 218 a_so = 0.59 fm 9625 1451 219 Coulomb: 9625 1451 220 C_coul = 1.3 9625 1451 221 r_c = 1.2452 fm 9625 1451 222 a_c = 0.545 fm 9625 1451 223 Deformation: 9625 1451 224 beta_2 = 0.213 9625 1451 225 beta_4 = 0.066 9625 1451 226 beta_6 = 0.0015 9625 1451 227 9625 1451 228 * Calculated strength function 9625 1451 229 S0= 1.12e-4 S1= 2.90e-4 R'= 9.29 fm (En=1 keV) 9625 1451 230 -------------------------------------------------- 9625 1451 231 9625 1451 232 Table 2. Level Scheme of Cm-240 9625 1451 233 ------------------- 9625 1451 234 No. Ex(MeV) J PI 9625 1451 235 ------------------- 9625 1451 236 0 0.00000 0 + * 9625 1451 237 1 0.03800 2 + * 9625 1451 238 2 0.12700 4 + * 9625 1451 239 3 0.26600 6 + * 9625 1451 240 4 0.45600 8 + * 9625 1451 241 ------------------- 9625 1451 242 *) Coupled levels in CC calculation 9625 1451 243 9625 1451 244 Table 3. Level density parameters 9625 1451 245 -------------------------------------------------------- 9625 1451 246 Nuclide a* Pair Eshell T E0 Ematch 9625 1451 247 1/MeV MeV MeV MeV MeV MeV 9625 1451 248 -------------------------------------------------------- 9625 1451 249 Cm-241 18.5675 0.7730 1.0938 0.3935 -0.8080 2.9546 9625 1451 250 Cm-240 18.5012 1.5492 1.2421 0.3627 0.2677 3.3492 9625 1451 251 Cm-239 18.4349 0.7762 1.2849 0.2896 0.0935 1.7762 9625 1451 252 Cm-238 18.3685 1.5557 1.3566 0.2895 0.8738 2.5557 9625 1451 253 -------------------------------------------------------- 9625 1451 254 9625 1451 255 Table 4. Fission barrier parameters 9625 1451 256 ---------------------------------------- 9625 1451 257 Nuclide V_A hw_A V_B hw_B 9625 1451 258 MeV MeV MeV MeV 9625 1451 259 ---------------------------------------- 9625 1451 260 Cm-241 5.800 0.800 6.200 0.600 9625 1451 261 Cm-240 6.000 1.040 5.000 0.600 9625 1451 262 Cm-239 6.300 0.800 5.000 0.520 9625 1451 263 Cm-238 6.000 1.040 5.000 0.600 9625 1451 264 ---------------------------------------- 9625 1451 265 9625 1451 266 Table 5. Level density above inner saddle 9625 1451 267 -------------------------------------------------------- 9625 1451 268 Nuclide a* Pair Eshell T E0 Ematch 9625 1451 269 1/MeV MeV MeV MeV MeV MeV 9625 1451 270 -------------------------------------------------------- 9625 1451 271 Cm-241 20.4242 0.9018 2.6000 0.3647 -2.0579 3.4018 9625 1451 272 Cm-240 20.3513 1.8074 2.6000 0.3300 -0.6156 3.8074 9625 1451 273 Cm-239 20.2784 0.9056 2.6000 0.3307 -1.5174 2.9056 9625 1451 274 Cm-238 20.2054 1.8150 2.6000 0.3313 -0.6081 3.8150 9625 1451 275 -------------------------------------------------------- 9625 1451 276 9625 1451 277 Table 6. Level density above outer saddle 9625 1451 278 -------------------------------------------------------- 9625 1451 279 Nuclide a* Pair Eshell T E0 Ematch 9625 1451 280 1/MeV MeV MeV MeV MeV MeV 9625 1451 281 -------------------------------------------------------- 9625 1451 282 Cm-241 20.4242 0.9018 0.5800 0.3862 -1.0599 3.2018 9625 1451 283 Cm-240 20.3513 1.8074 0.5400 0.3656 0.0996 3.8074 9625 1451 284 Cm-239 20.2784 0.9056 0.5000 0.3668 -0.8017 2.9056 9625 1451 285 Cm-238 20.2054 1.8150 0.4600 0.3680 0.1083 3.8150 9625 1451 286 -------------------------------------------------------- 9625 1451 287 9625 1451 288 Table 7. Gamma-ray strength function for Cm-241 9625 1451 289 -------------------------------------------------------- 9625 1451 290 * E1: ER = 11.55 (MeV) EG = 2.78 (MeV) SIG = 317.10 (mb) 9625 1451 291 ER = 14.33 (MeV) EG = 4.20 (MeV) SIG = 420.11 (mb) 9625 1451 292 * M1: ER = 6.59 (MeV) EG = 4.00 (MeV) SIG = 1.39 (mb) 9625 1451 293 * E2: ER = 10.12 (MeV) EG = 3.22 (MeV) SIG = 7.07 (mb) 9625 1451 294 -------------------------------------------------------- 9625 1451 295 9625 1451 296 9625 1451 297 References 9625 1451 298 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9625 1451 299 2) R.J.Tuttle: INDC(NDS)-107/G+Special, p.29 (1979). 9625 1451 300 3) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9625 1451 301 4) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9625 1451 302 5) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9625 1451 303 6) H.C.Britt, J.B.Wilhelmy: Nucl. Sci. Eng., 72, 222 (1979). 9625 1451 304 7) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9625 1451 305 8) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9625 1451 306 Japanese. 9625 1451 307 9) C.Kalbach: Phys. Rev. C33, 818 (1986). 9625 1451 308 10) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9625 1451 309 11) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9625 1451 310 12) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9625 1451 311 13) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9625 1451 312 14) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9625 1451 313 15) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9625 1451 314 9625 1451 315 1 451 327 19625 1451 316 2 151 4 19625 1451 317 3 4 27 19625 1451 318 3 16 12 19625 1451 319 3 17 8 19625 1451 320 3 18 137 19625 1451 321 3 102 164 19625 1451 322 8 4 2 19625 1451 323 8 16 2 19625 1451 324 8 17 2 19625 1451 325 8 18 2 19625 1451 326 8 102 2 19625 1451 327 9625 1 099999 9625 0 0 0 9.624000+4 2.379930+2 0 0 1 09625 2151 1 9.624000+4 1.000000+0 0 0 1 09625 2151 2 1.000000-5 3.200000+0 0 0 0 09625 2151 3 0.000000+0 9.290000-1 0 0 0 09625 2151 4 9625 2 099999 9625 0 0 0 9.624000+4 2.379930+2 0 0 0 09625 3 4 1 0.000000+0-3.800000+4 0 0 1 709625 3 4 2 70 2 9625 3 4 3 3.815970+4 0.000000+0 5.000000+4 8.600690-2 7.000000+4 2.573400-19625 3 4 4 1.000000+5 4.633380-1 1.109260+5 5.232611-1 1.200000+5 5.730335-19625 3 4 5 1.275340+5 6.074343-1 1.400000+5 6.576593-1 1.700000+5 7.543954-19625 3 4 6 2.000000+5 8.255420-1 2.500000+5 9.148124-1 2.671180+5 9.358719-19625 3 4 7 3.000000+5 9.682236-1 4.000000+5 1.023335+0 4.579160+5 1.032922+09625 3 4 8 5.000000+5 1.034742+0 6.000000+5 1.037859+0 7.000000+5 1.039384+09625 3 4 9 8.000000+5 1.053963+0 9.000000+5 1.066108+0 1.000000+6 1.076539+09625 3 4 10 1.100000+6 1.094482+0 1.200000+6 1.114310+0 1.300000+6 1.134562+09625 3 4 11 1.400000+6 1.154897+0 1.500000+6 1.171961+0 1.600000+6 1.189553+09625 3 4 12 1.700000+6 1.201855+0 1.800000+6 1.215257+0 1.900000+6 1.223332+09625 3 4 13 2.000000+6 1.232697+0 2.100000+6 1.236655+0 2.300000+6 1.248244+09625 3 4 14 2.500000+6 1.253795+0 2.700000+6 1.259883+0 3.000000+6 1.269186+09625 3 4 15 3.500000+6 1.290169+0 4.000000+6 1.329811+0 4.500000+6 1.379265+09625 3 4 16 5.000000+6 1.389524+0 5.500000+6 1.300505+0 6.000000+6 1.102935+09625 3 4 17 6.500000+6 9.108273-1 7.000000+6 7.674019-1 7.500000+6 6.696302-19625 3 4 18 8.000000+6 6.037437-1 8.500000+6 5.560987-1 9.000000+6 5.208172-19625 3 4 19 9.500000+6 4.923263-1 1.000000+7 4.687996-1 1.050000+7 4.485359-19625 3 4 20 1.100000+7 4.303449-1 1.150000+7 4.138859-1 1.200000+7 3.982479-19625 3 4 21 1.250000+7 3.837626-1 1.300000+7 3.696872-1 1.350000+7 3.566736-19625 3 4 22 1.400000+7 3.438849-1 1.450000+7 3.322049-1 1.500000+7 3.207190-19625 3 4 23 1.550000+7 3.103176-1 1.600000+7 3.001033-1 1.650000+7 2.909251-19625 3 4 24 1.700000+7 2.819335-1 1.750000+7 2.738560-1 1.800000+7 2.659362-19625 3 4 25 1.850000+7 2.588251-1 1.900000+7 2.518613-1 1.950000+7 2.455914-19625 3 4 26 2.000000+7 2.394519-1 9625 3 4 27 9625 3 099999 9.624000+4 2.379930+2 0 0 0 09625 3 16 1 -7.537880+6-7.537880+6 0 0 1 269625 3 16 2 26 2 9625 3 16 3 7.569560+6 0.000000+0 8.000000+6 6.989240-4 8.500000+6 3.302190-39625 3 16 4 9.000000+6 5.987900-3 9.500000+6 1.028360-2 1.000000+7 1.482970-29625 3 16 5 1.050000+7 2.046750-2 1.100000+7 2.867410-2 1.150000+7 3.842820-29625 3 16 6 1.200000+7 4.926590-2 1.250000+7 6.110020-2 1.300000+7 7.355870-29625 3 16 7 1.350000+7 8.618640-2 1.400000+7 9.734610-2 1.450000+7 1.032090-19625 3 16 8 1.500000+7 1.021980-1 1.550000+7 9.574720-2 1.600000+7 8.626340-29625 3 16 9 1.650000+7 7.566940-2 1.700000+7 6.583660-2 1.750000+7 5.727390-29625 3 16 10 1.800000+7 5.001500-2 1.850000+7 4.440600-2 1.900000+7 3.979160-29625 3 16 11 1.950000+7 3.641730-2 2.000000+7 3.356820-2 9625 3 16 12 9625 3 099999 9.624000+4 2.379930+2 0 0 0 09625 3 17 1 -1.381310+7-1.381310+7 0 0 1 139625 3 17 2 13 2 9625 3 17 3 1.387110+7 0.000000+0 1.450000+7 3.428100-6 1.500000+7 2.313910-59625 3 17 4 1.550000+7 7.739970-5 1.600000+7 1.284170-4 1.650000+7 1.813720-49625 3 17 5 1.700000+7 3.172970-4 1.750000+7 4.460110-4 1.800000+7 6.271750-49625 3 17 6 1.850000+7 8.899780-4 1.900000+7 1.259570-3 1.950000+7 1.750960-39625 3 17 7 2.000000+7 2.360490-3 9625 3 17 8 9625 3 099999 9.624000+4 2.379930+2 0 0 0 09625 3 18 1 2.006000+8 2.006000+8 0 0 1 4019625 3 18 2 401 2 9625 3 18 3 1.000000-5 1.502839+3 1.103037-5 1.430934+3 1.216691-5 1.362469+39625 3 18 4 1.342055-5 1.297281+3 1.480336-5 1.235213+3 1.632865-5 1.176115+39625 3 18 5 1.801111-5 1.119845+3 1.986691-5 1.066268+3 2.191394-5 1.015255+39625 3 18 6 2.417189-5 9.666837+2 2.666248-5 9.204368+2 2.940971-5 8.764033+29625 3 18 7 3.243999-5 8.344772+2 3.578251-5 7.945578+2 3.946943-5 7.565489+29625 3 18 8 4.353624-5 7.203592+2 4.802208-5 6.859016+2 5.297013-5 6.530933+29625 3 18 9 5.842801-5 6.218553+2 6.444825-5 5.921124+2 7.108881-5 5.637932+29625 3 18 10 7.841358-5 5.368294+2 8.649308-5 5.111562+2 9.540506-5 4.867118+29625 3 18 11 1.052353-4 4.634374+2 1.160784-4 4.412769+2 1.280388-4 4.201771+29625 3 18 12 1.412315-4 4.000871+2 1.557836-4 3.809586+2 1.718351-4 3.627455+29625 3 18 13 1.895404-4 3.454039+2 2.090701-4 3.288921+2 2.306120-4 3.131704+29625 3 18 14 2.543736-4 2.982008+2 2.805835-4 2.839474+2 3.094939-4 2.703757+29625 3 18 15 3.413832-4 2.574532+2 3.765583-4 2.451488+2 4.153577-4 2.334327+29625 3 18 16 4.581549-4 2.222769+2 5.053618-4 2.116545+2 5.574328-4 2.015399+29625 3 18 17 6.148689-4 1.919089+2 6.782232-4 1.827383+2 7.481052-4 1.740060+29625 3 18 18 8.251877-4 1.656911+2 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