JENDL-5 (Neutron sublibrary (activation cs)) Cf-248 0 0 0 0 9.824800+4 2.459410+2 0 0 6 19849 1451 1 0.000000+0 1.000000+0 0 0 0 69849 1451 2 1.000000+0 2.000000+7 0 0 10 59849 1451 3 2.936000+2 0.000000+0 4 0 306 129849 1451 4 98-Cf-248 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9849 1451 5 DIST-DEC21 20100304 9849 1451 6 ----JENDL-5 MATERIAL 9849 9849 1451 7 -----INCIDENT NEUTRON DATA 9849 1451 8 ------ENDF-6 FORMAT 9849 1451 9 9849 1451 10 History 9849 1451 11 07-10 Theoretical calculation was performed with CCONE code. 9849 1451 12 07-11 Data were compiled as JENDL/AC-2008/1/. 9849 1451 13 10-02 Data of prompt gamma rays due to fission were given. 9849 1451 14 10-03 Covariance data were given. 9849 1451 15 21-11 revised by O.Iwamoto 9849 1451 16 (MF3/MT19-21,38) deleted 9849 1451 17 (MF8/MT4,16-18,102) added 9849 1451 18 9849 1451 19 9849 1451 20 MF=1 General information 9849 1451 21 MT=452 Number of Neutrons per fission 9849 1451 22 Sum of MT's=455 and 456. 9849 1451 23 9849 1451 24 MT=455 Delayed neutron data 9849 1451 25 Estimated from systematics by Tuttle/2/, Benedetti et al./3/ 9849 1451 26 and Waldo et al./4/ 9849 1451 27 9849 1451 28 MT=456 Number of prompt neutrons per fission 9849 1451 29 Estimated from Howerton's systematics/5/. 9849 1451 30 9849 1451 31 9849 1451 32 MF= 2 Resonance parameters 9849 1451 33 MT=151 9849 1451 34 No resonance parameters are given. 9849 1451 35 9849 1451 36 9849 1451 37 Thermal cross sections and resonance integrals (at 300K) 9849 1451 38 ------------------------------------------------------- 9849 1451 39 0.0253 eV reson. integ.(*) 9849 1451 40 (barns) (barns) 9849 1451 41 ------------------------------------------------------- 9849 1451 42 total 2405.8 9849 1451 43 elastic 10.62 9849 1451 44 fission 693.7 312 9849 1451 45 capture 1700.5 733 9849 1451 46 ------------------------------------------------------- 9849 1451 47 (*) In the energy range from 0.5 eV to 10 MeV. 9849 1451 48 9849 1451 49 9849 1451 50 MF= 3 Neutron cross sections 9849 1451 51 Below 7.0 eV: 9849 1451 52 * Elastic scattering cross section is 10.6 b calculated from 9849 1451 53 scattering radius of 9.200 fm/6/. 9849 1451 54 * Fission cross section at 0.0253 eV was assumed to be 700 b 9849 1451 55 from systematics. 9849 1451 56 * Capture cross section at 0.0253 eV was assumed to be 1700 b 9849 1451 57 from the fission cross section and capture to fission ratio 9849 1451 58 calculated at 1 eV with CCONE code/6/. 9849 1451 59 9849 1451 60 Above 7.0 eV: 9849 1451 61 Cross sections calculated with CCONE code/6/ were adopted. 9849 1451 62 9849 1451 63 MT= 1 Total cross section 9849 1451 64 The cross section was calculated with CC OMP of Soukhovitskii 9849 1451 65 et al./7/ 9849 1451 66 9849 1451 67 9849 1451 68 MF= 4 Angular distributions of secondary neutrons 9849 1451 69 MT=2 Elastic scattering 9849 1451 70 Calculated with CCONE code/6/. 9849 1451 71 9849 1451 72 MT=18 Fission 9849 1451 73 Isotropic distributions in the laboratory system were assumed.9849 1451 74 9849 1451 75 9849 1451 76 MF= 5 Energy distributions of secondary neutrons 9849 1451 77 MT=18 Prompt neutrons 9849 1451 78 Calculated with CCONE code/6/. 9849 1451 79 9849 1451 80 9849 1451 81 MF= 6 Energy-angle distributions 9849 1451 82 Calculated with CCONE code/6/. 9849 1451 83 Distributions from fission (MT=18) are not included. 9849 1451 84 9849 1451 85 9849 1451 86 MF=12 Photon production multiplicities 9849 1451 87 MT=18 Fission 9849 1451 88 Calculated from the total energy released by the prompt 9849 1451 89 gamma-rays due to fission which was estimated from its 9849 1451 90 systematics, and the average energy of gamma-rays. 9849 1451 91 9849 1451 92 9849 1451 93 MF=14 Photon angular distributions 9849 1451 94 MT=18 Fission 9849 1451 95 Isotoropic distributions were assumed. 9849 1451 96 9849 1451 97 9849 1451 98 MF=15 Continuous photon energy spectra 9849 1451 99 MT=18 Fission 9849 1451 100 Experimental data measured by Verbinski et al./8/ for 9849 1451 101 Pu-239 thermal fission were adopted. 9849 1451 102 9849 1451 103 9849 1451 104 MF=31 Covariances of average number of neutrons per fission 9849 1451 105 MT=452 Number of neutrons per fission 9849 1451 106 Sum of covariances for MT=455 and MT=456. 9849 1451 107 9849 1451 108 MT=455 9849 1451 109 Error of 15% was assumed. 9849 1451 110 9849 1451 111 MT=456 9849 1451 112 Covariance was obtained by fitting a linear function to the 9849 1451 113 at 0.0 and 5.0 MeV with an uncertainty of 10%. 9849 1451 114 9849 1451 115 9849 1451 116 MF=33 Covariances of neutron cross sections 9849 1451 117 Covariances were given to all the cross sections by using 9849 1451 118 KALMAN code/9/ and the covariances of model parameters 9849 1451 119 used in the cross-section calculations. 9849 1451 120 9849 1451 121 For the following cross sections, standard deviations in the 9849 1451 122 energy region below 7.0 eV were assumed as follows: 9849 1451 123 9849 1451 124 Total 69 % 9849 1451 125 Elastic scattering 90 % 9849 1451 126 Fission 90 % 9849 1451 127 Capture 90 % 9849 1451 128 9849 1451 129 9849 1451 130 MF=34 Covariances for Angular Distributions 9849 1451 131 MT=2 Elastic scattering 9849 1451 132 Covariances were given only to P1 components. 9849 1451 133 9849 1451 134 9849 1451 135 MF=35 Covariances for Energy Distributions 9849 1451 136 MT=18 Fission spectra 9849 1451 137 Estimated with CCONE and KALMAN codes. 9849 1451 138 9849 1451 139 9849 1451 140 ***************************************************************** 9849 1451 141 Calculation with CCONE code 9849 1451 142 ***************************************************************** 9849 1451 143 9849 1451 144 Models and parameters used in the CCONE/6/ calculation 9849 1451 145 1) Coupled channel optical model 9849 1451 146 Levels in the rotational band were included. Optical model 9849 1451 147 potential and coupled levels are shown in Table 1. 9849 1451 148 9849 1451 149 2) Two-component exciton model/10/ 9849 1451 150 * Global parametrization of Koning-Duijvestijn/11/ 9849 1451 151 was used. 9849 1451 152 * Gamma emission channel/12/ was added to simulate direct 9849 1451 153 and semi-direct capture reaction. 9849 1451 154 9849 1451 155 3) Hauser-Feshbach statistical model 9849 1451 156 * Moldauer width fluctuation correction/13/ was included. 9849 1451 157 * Neutron, gamma and fission decay channel were included. 9849 1451 158 * Transmission coefficients of neutrons were taken from 9849 1451 159 coupled channel calculation in Table 1. 9849 1451 160 * The level scheme of the target is shown in Table 2. 9849 1451 161 * Level density formula of constant temperature and Fermi-gas 9849 1451 162 model were used with shell energy correction and collective 9849 1451 163 enhancement factor. Parameters are shown in Table 3. 9849 1451 164 * Fission channel: 9849 1451 165 Double humped fission barriers were assumed. 9849 1451 166 Fission barrier penetrabilities were calculated with 9849 1451 167 Hill-Wheler formula/14/. Fission barrier parameters were 9849 1451 168 shown in Table 4. Transition state model was used and 9849 1451 169 continuum levels are assumed above the saddles. The level 9849 1451 170 density parameters for inner and outer saddles are shown in 9849 1451 171 Tables 5 and 6, respectively. 9849 1451 172 * Gamma-ray strength function of Kopecky et al/15/,/16/ 9849 1451 173 was used. The prameters are shown in Table 7. 9849 1451 174 9849 1451 175 9849 1451 176 ------------------------------------------------------------------9849 1451 177 Tables 9849 1451 178 ------------------------------------------------------------------9849 1451 179 9849 1451 180 Table 1. Coupled channel calculation 9849 1451 181 -------------------------------------------------- 9849 1451 182 * rigid rotor model was applied 9849 1451 183 * coupled levels = 0,1,2,3 (see Table 2) 9849 1451 184 * optical potential parameters /7/ 9849 1451 185 Volume: 9849 1451 186 V_0 = 49.97 MeV 9849 1451 187 lambda_HF = 0.01004 1/MeV 9849 1451 188 C_viso = 15.9 MeV 9849 1451 189 A_v = 12.04 MeV 9849 1451 190 B_v = 81.36 MeV 9849 1451 191 E_a = 385 MeV 9849 1451 192 r_v = 1.2568 fm 9849 1451 193 a_v = 0.633 fm 9849 1451 194 Surface: 9849 1451 195 W_0 = 17.2 MeV 9849 1451 196 B_s = 11.19 MeV 9849 1451 197 C_s = 0.01361 1/MeV 9849 1451 198 C_wiso = 23.5 MeV 9849 1451 199 r_s = 1.1803 fm 9849 1451 200 a_s = 0.601 fm 9849 1451 201 Spin-orbit: 9849 1451 202 V_so = 5.75 MeV 9849 1451 203 lambda_so = 0.005 1/MeV 9849 1451 204 W_so = -3.1 MeV 9849 1451 205 B_so = 160 MeV 9849 1451 206 r_so = 1.1214 fm 9849 1451 207 a_so = 0.59 fm 9849 1451 208 Coulomb: 9849 1451 209 C_coul = 1.3 9849 1451 210 r_c = 1.2452 fm 9849 1451 211 a_c = 0.545 fm 9849 1451 212 Deformation: 9849 1451 213 beta_2 = 0.213 9849 1451 214 beta_4 = 0.066 9849 1451 215 beta_6 = 0.0015 9849 1451 216 9849 1451 217 * Calculated strength function 9849 1451 218 S0= 1.44e-4 S1= 2.46e-4 R'= 9.20 fm (En=1 keV) 9849 1451 219 -------------------------------------------------- 9849 1451 220 9849 1451 221 Table 2. Level Scheme of Cf-248 9849 1451 222 ------------------- 9849 1451 223 No. Ex(MeV) J PI 9849 1451 224 ------------------- 9849 1451 225 0 0.00000 0 + * 9849 1451 226 1 0.04153 2 + * 9849 1451 227 2 0.13781 4 + * 9849 1451 228 3 0.28500 6 + * 9849 1451 229 4 0.59220 2 - 9849 1451 230 5 0.63000 3 - 9849 1451 231 6 0.67700 4 - 9849 1451 232 7 0.73500 5 - 9849 1451 233 8 0.80600 6 - 9849 1451 234 ------------------- 9849 1451 235 *) Coupled levels in CC calculation 9849 1451 236 9849 1451 237 Table 3. Level density parameters 9849 1451 238 -------------------------------------------------------- 9849 1451 239 Nuclide a* Pair Eshell T E0 Ematch 9849 1451 240 1/MeV MeV MeV MeV MeV MeV 9849 1451 241 -------------------------------------------------------- 9849 1451 242 Cf-249 19.0966 0.7605 0.7689 0.3773 -0.6847 2.7641 9849 1451 243 Cf-248 19.0305 1.5240 0.7495 0.3921 -0.0631 3.7096 9849 1451 244 Cf-247 18.9645 0.7635 0.5924 0.3748 -0.6176 2.6898 9849 1451 245 Cf-246 18.8984 1.5302 0.7686 0.4030 -0.1574 3.8448 9849 1451 246 -------------------------------------------------------- 9849 1451 247 9849 1451 248 Table 4. Fission barrier parameters 9849 1451 249 ---------------------------------------- 9849 1451 250 Nuclide V_A hw_A V_B hw_B 9849 1451 251 MeV MeV MeV MeV 9849 1451 252 ---------------------------------------- 9849 1451 253 Cf-249 6.700 1.200 5.900 0.800 9849 1451 254 Cf-248 6.200 1.040 5.400 0.600 9849 1451 255 Cf-247 6.700 1.000 5.900 0.800 9849 1451 256 Cf-246 6.200 1.040 5.400 0.600 9849 1451 257 ---------------------------------------- 9849 1451 258 9849 1451 259 Table 5. Level density above inner saddle 9849 1451 260 -------------------------------------------------------- 9849 1451 261 Nuclide a* Pair Eshell T E0 Ematch 9849 1451 262 1/MeV MeV MeV MeV MeV MeV 9849 1451 263 -------------------------------------------------------- 9849 1451 264 Cf-249 20.0514 0.8872 2.5000 0.3486 -1.7837 3.0872 9849 1451 265 Cf-248 21.3142 1.7780 2.5000 0.3226 -0.6352 3.7780 9849 1451 266 Cf-247 21.2402 0.8908 2.5000 0.3232 -1.5224 2.8908 9849 1451 267 Cf-246 21.1662 1.7852 2.5000 0.3238 -0.6280 3.7852 9849 1451 268 -------------------------------------------------------- 9849 1451 269 9849 1451 270 Table 6. Level density above outer saddle 9849 1451 271 -------------------------------------------------------- 9849 1451 272 Nuclide a* Pair Eshell T E0 Ematch 9849 1451 273 1/MeV MeV MeV MeV MeV MeV 9849 1451 274 -------------------------------------------------------- 9849 1451 275 Cf-249 20.0514 0.8872 0.9200 0.3794 -1.0059 3.0872 9849 1451 276 Cf-248 21.3142 1.7780 0.8800 0.3522 0.0693 3.7780 9849 1451 277 Cf-247 21.2402 0.8908 0.8400 0.3533 -0.8173 2.8908 9849 1451 278 Cf-246 21.1662 1.7852 0.8000 0.3544 0.0777 3.7852 9849 1451 279 -------------------------------------------------------- 9849 1451 280 9849 1451 281 Table 7. Gamma-ray strength function for Cf-249 9849 1451 282 -------------------------------------------------------- 9849 1451 283 K0 = 1.500 E0 = 4.500 (MeV) 9849 1451 284 * E1: ER = 11.38 (MeV) EG = 2.71 (MeV) SIG = 254.06 (mb) 9849 1451 285 ER = 14.28 (MeV) EG = 4.18 (MeV) SIG = 508.13 (mb) 9849 1451 286 * M1: ER = 6.52 (MeV) EG = 4.00 (MeV) SIG = 1.81 (mb) 9849 1451 287 * E2: ER = 10.01 (MeV) EG = 3.12 (MeV) SIG = 7.36 (mb) 9849 1451 288 -------------------------------------------------------- 9849 1451 289 9849 1451 290 9849 1451 291 References 9849 1451 292 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9849 1451 293 2) R.J.Tuttld: INDC(NDS)-107/G+Special, p.29 (1979). 9849 1451 294 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 9849 1451 295 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 9849 1451 296 5) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9849 1451 297 6) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9849 1451 298 7) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9849 1451 299 8) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9849 1451 300 9) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9849 1451 301 Japanese. 9849 1451 302 10) C.Kalbach: Phys. Rev. C33, 818 (1986). 9849 1451 303 11) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9849 1451 304 12) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9849 1451 305 13) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9849 1451 306 14) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9849 1451 307 15) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9849 1451 308 16) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9849 1451 309 9849 1451 310 1 451 322 19849 1451 311 2 151 4 19849 1451 312 3 4 28 19849 1451 313 3 16 12 19849 1451 314 3 17 8 19849 1451 315 3 18 129 19849 1451 316 3 102 154 19849 1451 317 8 4 2 19849 1451 318 8 16 2 19849 1451 319 8 17 2 19849 1451 320 8 18 2 19849 1451 321 8 102 2 19849 1451 322 9849 1 099999 9849 0 0 0 9.824800+4 2.459410+2 0 0 1 09849 2151 1 9.824800+4 1.000000+0 0 0 1 09849 2151 2 1.000000-5 7.000000+0 0 0 0 09849 2151 3 0.000000+0 9.200000-1 0 0 0 09849 2151 4 9849 2 099999 9849 0 0 0 9.824800+4 2.459410+2 0 0 0 09849 3 4 1 0.000000+0-4.153000+4 0 0 1 759849 3 4 2 75 2 9849 3 4 3 4.169890+4 0.000000+0 5.000000+4 9.708380-2 7.000000+4 3.274070-19849 3 4 4 1.000000+5 5.840640-1 1.108960+5 6.511812-1 1.200000+5 7.072682-19849 3 4 5 1.383700+5 8.081199-1 1.400000+5 8.168418-1 1.700000+5 9.612076-19849 3 4 6 2.000000+5 1.103326+0 2.500000+5 1.261977+0 2.861590+5 1.364500+09849 3 4 7 3.000000+5 1.404610+0 4.000000+5 1.525498+0 5.000000+5 1.650852+09849 3 4 8 5.946080+5 1.661013+0 6.000000+5 1.684083+0 6.325620+5 1.734585+09849 3 4 9 6.797530+5 1.810383+0 7.000000+5 1.842605+0 7.379880+5 1.877352+09849 3 4 10 7.379890+5 1.877352+0 8.000000+5 1.914811+0 8.092770+5 1.918790+09849 3 4 11 9.000000+5 1.944803+0 1.000000+6 1.965519+0 1.100000+6 1.997314+09849 3 4 12 1.200000+6 2.027627+0 1.300000+6 2.057127+0 1.400000+6 2.083933+09849 3 4 13 1.500000+6 2.102377+0 1.600000+6 2.120428+0 1.700000+6 2.124785+09849 3 4 14 1.800000+6 2.127242+0 1.900000+6 2.118338+0 2.000000+6 2.108846+09849 3 4 15 2.100000+6 2.092090+0 2.300000+6 2.053981+0 2.500000+6 2.011092+09849 3 4 16 2.700000+6 1.967934+0 3.000000+6 1.909336+0 3.500000+6 1.827386+09849 3 4 17 4.000000+6 1.788248+0 4.500000+6 1.790416+0 5.000000+6 1.810406+09849 3 4 18 5.500000+6 1.776853+0 6.000000+6 1.575896+0 6.500000+6 1.290864+09849 3 4 19 7.000000+6 1.046330+0 7.500000+6 8.673280-1 8.000000+6 7.411661-19849 3 4 20 8.500000+6 6.536642-1 9.000000+6 5.919356-1 9.500000+6 5.467888-19849 3 4 21 1.000000+7 5.123145-1 1.050000+7 4.846331-1 1.100000+7 4.615584-19849 3 4 22 1.150000+7 4.414390-1 1.200000+7 4.231833-1 1.250000+7 4.064859-19849 3 4 23 1.300000+7 3.908323-1 1.350000+7 3.762325-1 1.400000+7 3.625766-19849 3 4 24 1.450000+7 3.497297-1 1.500000+7 3.376240-1 1.550000+7 3.265808-19849 3 4 25 1.600000+7 3.156640-1 1.650000+7 3.059759-1 1.700000+7 2.964323-19849 3 4 26 1.750000+7 2.878465-1 1.800000+7 2.794935-1 1.850000+7 2.719645-19849 3 4 27 1.900000+7 2.645594-1 1.950000+7 2.578832-1 2.000000+7 2.513227-19849 3 4 28 9849 3 099999 9.824800+4 2.459410+2 0 0 0 09849 3 16 1 -6.968180+6-6.968180+6 0 0 1 279849 3 16 2 27 2 9849 3 16 3 6.996510+6 0.000000+0 7.500000+6 2.269930-2 8.000000+6 9.561550-29849 3 16 4 8.500000+6 1.765730-1 9.000000+6 2.391890-1 9.500000+6 2.775300-19849 3 16 5 1.000000+7 2.965440-1 1.050000+7 3.086040-1 1.100000+7 3.137760-19849 3 16 6 1.150000+7 3.179950-1 1.200000+7 3.288360-1 1.250000+7 3.382900-19849 3 16 7 1.300000+7 3.501750-1 1.350000+7 3.567530-1 1.400000+7 3.513240-19849 3 16 8 1.450000+7 3.340660-1 1.500000+7 3.057250-1 1.550000+7 2.696470-19849 3 16 9 1.600000+7 2.352090-1 1.650000+7 2.029200-1 1.700000+7 1.744600-19849 3 16 10 1.750000+7 1.537610-1 1.800000+7 1.356880-1 1.850000+7 1.215850-19849 3 16 11 1.900000+7 1.107060-1 1.950000+7 1.022570-1 2.000000+7 9.588300-29849 3 16 12 9849 3 099999 9.824800+4 2.459410+2 0 0 0 09849 3 17 1 -1.299460+7-1.299460+7 0 0 1 159849 3 17 2 15 2 9849 3 17 3 1.304740+7 0.000000+0 1.350000+7 9.542400-5 1.400000+7 2.397870-39849 3 17 4 1.450000+7 8.499550-3 1.500000+7 1.746920-2 1.550000+7 2.802890-29849 3 17 5 1.600000+7 3.834190-2 1.650000+7 4.310740-2 1.700000+7 5.050340-29849 3 17 6 1.750000+7 5.250170-2 1.800000+7 5.322630-2 1.850000+7 5.353060-29849 3 17 7 1.900000+7 5.366340-2 1.950000+7 5.410640-2 2.000000+7 5.272540-29849 3 17 8 9849 3 099999 9.824800+4 2.459410+2 0 0 0 09849 3 18 1 2.116000+8 2.116000+8 0 0 1 3779849 3 18 2 377 2 9849 3 18 3 1.000000-5 3.506545+4 1.103037-5 3.338770+4 1.216691-5 3.179023+49849 3 18 4 1.342055-5 3.026922+4 1.480336-5 2.882099+4 1.632865-5 2.744207+49849 3 18 5 1.801111-5 2.612914+4 1.986691-5 2.487905+4 2.191394-5 2.368878+49849 3 18 6 2.417189-5 2.255548+4 2.666248-5 2.147641+4 2.940971-5 2.044899+49849 3 18 7 3.243999-5 1.947074+4 3.578251-5 1.853932+4 3.946943-5 1.765247+49849 3 18 8 4.353624-5 1.680807+4 4.802208-5 1.600408+4 5.297013-5 1.523857+49849 3 18 9 5.842801-5 1.450971+4 6.444825-5 1.381573+4 7.108881-5 1.315496+49849 3 18 10 7.841358-5 1.252583+4 8.649308-5 1.192680+4 9.540506-5 1.135645+49849 3 18 11 1.052353-4 1.081340+4 1.160784-4 1.029633+4 1.280388-4 9.804017+39849 3 18 12 1.412315-4 9.335263+3 1.557836-4 8.888943+3 1.718351-4 8.463981+39849 3 18 13 1.895404-4 8.059354+3 2.090701-4 7.674088+3 2.306120-4 7.307256+39849 3 18 14 2.543736-4 6.957973+3 2.805835-4 6.625399+3 3.094939-4 6.308733+39849 3 18 15 3.413832-4 6.007213+3 3.765583-4 5.720114+3 4.153577-4 5.446743+39849 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