JENDL-5 (Neutron sublibrary (activation cs)) Bk-245 0 0 0 0 9.724500+4 2.429610+2 0 0 6 19740 1451 1 0.000000+0 1.000000+0 0 0 0 69740 1451 2 1.000000+0 2.000000+7 0 0 10 59740 1451 3 2.936000+2 0.000000+0 4 0 305 129740 1451 4 97-Bk-245 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9740 1451 5 DIST-DEC21 20100304 9740 1451 6 ----JENDL-5 MATERIAL 9740 9740 1451 7 -----INCIDENT NEUTRON DATA 9740 1451 8 ------ENDF-6 FORMAT 9740 1451 9 9740 1451 10 History 9740 1451 11 07-10 Theoretical calculation was performed with CCONE code. 9740 1451 12 07-11 Data were compiled as JENDL/AC-2008/1/. 9740 1451 13 10-02 Data of prompt gamma rays due to fission were given. 9740 1451 14 10-03 Covariance data were given. 9740 1451 15 21-11 revised by O.Iwamoto 9740 1451 16 (MF3/MT19-21,38) deleted 9740 1451 17 (MF8/MT4,16-18,102) added 9740 1451 18 9740 1451 19 9740 1451 20 MF=1 General information 9740 1451 21 MT=452 Number of Neutrons per fission 9740 1451 22 Sum of MT's=455 and 456. 9740 1451 23 9740 1451 24 MT=455 Delayed neutron data 9740 1451 25 Estimated from systematics by Tuttle/2/, Benedetti et al. 9740 1451 26 /3/ and Waldo et al./4/ 9740 1451 27 9740 1451 28 MT=456 Number of prompt neutrons per fission 9740 1451 29 Estimated from Howerton's systematics/5/. 9740 1451 30 9740 1451 31 9740 1451 32 MF= 2 Resonance parameters 9740 1451 33 MT=151 9740 1451 34 No resonance parameters are given. 9740 1451 35 9740 1451 36 9740 1451 37 Thermal cross sections and resonance integrals (at 300K) 9740 1451 38 ------------------------------------------------------- 9740 1451 39 0.0253 eV reson. integ.(*) 9740 1451 40 (barns) (barns) 9740 1451 41 ------------------------------------------------------- 9740 1451 42 total 1013.9 9740 1451 43 elastic 10.32 9740 1451 44 fission 2.902 5.29 9740 1451 45 capture 1000.4 1080 9740 1451 46 ------------------------------------------------------- 9740 1451 47 (*) In the energy range from 0.5 eV to 10 MeV. 9740 1451 48 9740 1451 49 9740 1451 50 MF= 3 Neutron cross sections 9740 1451 51 Below 0.3 eV: 9740 1451 52 * Elastic scattering cross section is 10.3 b calculated from 9740 1451 53 scattering radius of 9.049 fm/6/. 9740 1451 54 * Fission cross section is in the 1/v shape. 9740 1451 55 CCONE calculation was extrapolated to 1.0e-5 eV. 9740 1451 56 * Capture cross section is in the 1/v shape. 9740 1451 57 Cross section of 1000 b at 0.0253 eV was assumed. 9740 1451 58 9740 1451 59 Above 0.3 eV: 9740 1451 60 Cross sections calculated with CCONE code/6/ were adopted. 9740 1451 61 9740 1451 62 MT= 1 Total cross section 9740 1451 63 The cross section was calculated with CC OMP of Soukhovitskii 9740 1451 64 et al./7/ 9740 1451 65 9740 1451 66 9740 1451 67 MF= 4 Angular distributions of secondary neutrons 9740 1451 68 MT=2 Elastic scattering 9740 1451 69 Calculated with CCONE code/6/. 9740 1451 70 9740 1451 71 MT=18 Fission 9740 1451 72 Isotropic distributions in the laboratory system were assumed.9740 1451 73 9740 1451 74 9740 1451 75 MF= 5 Energy distributions of secondary neutrons 9740 1451 76 MT=18 Prompt neutrons 9740 1451 77 Calculated with CCONE code/6/. 9740 1451 78 9740 1451 79 9740 1451 80 MF= 6 Energy-angle distributions 9740 1451 81 Calculated with CCONE code/6/. 9740 1451 82 Distributions from fission (MT=18) are not included. 9740 1451 83 9740 1451 84 9740 1451 85 MF=12 Photon production multiplicities 9740 1451 86 MT=18 Fission 9740 1451 87 Calculated from the total energy released by the prompt 9740 1451 88 gamma-rays due to fission which was estimated from its 9740 1451 89 systematics, and the average energy of gamma-rays. 9740 1451 90 9740 1451 91 9740 1451 92 MF=14 Photon angular distributions 9740 1451 93 MT=18 Fission 9740 1451 94 Isotoropic distributions were assumed. 9740 1451 95 9740 1451 96 9740 1451 97 MF=15 Continuous photon energy spectra 9740 1451 98 MT=18 Fission 9740 1451 99 Experimental data measured by Verbinski et al./8/ for 9740 1451 100 Pu-239 thermal fission were adopted. 9740 1451 101 9740 1451 102 9740 1451 103 MF=31 Covariances of average number of neutrons per fission 9740 1451 104 MT=452 Number of neutrons per fission 9740 1451 105 Sum of covariances for MT=455 and MT=456. 9740 1451 106 9740 1451 107 MT=455 9740 1451 108 Error of 15% was assumed. 9740 1451 109 9740 1451 110 MT=456 9740 1451 111 Covariance was obtained by fitting a linear function to the 9740 1451 112 at 0.0 and 5.0 MeV with an uncertainty of 10%. 9740 1451 113 9740 1451 114 9740 1451 115 MF=33 Covariances of neutron cross sections 9740 1451 116 Covariances were given to all the cross sections by using 9740 1451 117 KALMAN code/9/ and the covariances of model parameters 9740 1451 118 used in the cross-section calculations. 9740 1451 119 9740 1451 120 Covariances of the fission cross section were determined from 9740 1451 121 experimental data. 9740 1451 122 9740 1451 123 For the following cross sections, standard deviations in the 9740 1451 124 energy region below 0.3 eV were assumed as follows: 9740 1451 125 9740 1451 126 Total 89 % 9740 1451 127 Elastic scattering 90 % 9740 1451 128 Fission 90 % 9740 1451 129 Capture 90 % 9740 1451 130 9740 1451 131 9740 1451 132 MF=34 Covariances for Angular Distributions 9740 1451 133 MT=2 Elastic scattering 9740 1451 134 Covariances were given only to P1 components. 9740 1451 135 9740 1451 136 9740 1451 137 MF=35 Covariances for Energy Distributions 9740 1451 138 MT=18 Fission spectra 9740 1451 139 Estimated with CCONE and KALMAN codes. 9740 1451 140 9740 1451 141 9740 1451 142 ***************************************************************** 9740 1451 143 Calculation with CCONE code 9740 1451 144 ***************************************************************** 9740 1451 145 9740 1451 146 Models and parameters used in the CCONE/6/ calculation 9740 1451 147 1) Coupled channel optical model 9740 1451 148 Levels in the rotational band were included. Optical model 9740 1451 149 potential and coupled levels are shown in Table 1. 9740 1451 150 9740 1451 151 2) Two-component exciton model/10/ 9740 1451 152 * Global parametrization of Koning-Duijvestijn/11/ 9740 1451 153 was used. 9740 1451 154 * Gamma emission channel/12/ was added to simulate direct 9740 1451 155 and semi-direct capture reaction. 9740 1451 156 9740 1451 157 3) Hauser-Feshbach statistical model 9740 1451 158 * Moldauer width fluctuation correction/13/ was included. 9740 1451 159 * Neutron, gamma and fission decay channel were included. 9740 1451 160 * Transmission coefficients of neutrons were taken from 9740 1451 161 coupled channel calculation in Table 1. 9740 1451 162 * The level scheme of the target is shown in Table 2. 9740 1451 163 * Level density formula of constant temperature and Fermi-gas 9740 1451 164 model were used with shell energy correction and collective 9740 1451 165 enhancement factor. Parameters are shown in Table 3. 9740 1451 166 * Fission channel: 9740 1451 167 Double humped fission barriers were assumed. 9740 1451 168 Fission barrier penetrabilities were calculated with 9740 1451 169 Hill-Wheler formula/14/. Fission barrier parameters were 9740 1451 170 shown in Table 4. Transition state model was used and 9740 1451 171 continuum levels are assumed above the saddles. The level 9740 1451 172 density parameters for inner and outer saddles are shown in 9740 1451 173 Tables 5 and 6, respectively. 9740 1451 174 * Gamma-ray strength function of Kopecky et al/15/,/16/ 9740 1451 175 was used. The prameters are shown in Table 7. 9740 1451 176 9740 1451 177 9740 1451 178 ------------------------------------------------------------------9740 1451 179 Tables 9740 1451 180 ------------------------------------------------------------------9740 1451 181 9740 1451 182 Table 1. Coupled channel calculation 9740 1451 183 -------------------------------------------------- 9740 1451 184 * rigid rotor model was applied 9740 1451 185 * coupled levels = 0,1,3,5 (see Table 2) 9740 1451 186 * optical potential parameters /7/ 9740 1451 187 Volume: 9740 1451 188 V_0 = 49.97 MeV 9740 1451 189 lambda_HF = 0.01004 1/MeV 9740 1451 190 C_viso = 15.9 MeV 9740 1451 191 A_v = 12.04 MeV 9740 1451 192 B_v = 81.36 MeV 9740 1451 193 E_a = 385 MeV 9740 1451 194 r_v = 1.2568 fm 9740 1451 195 a_v = 0.633 fm 9740 1451 196 Surface: 9740 1451 197 W_0 = 17.2 MeV 9740 1451 198 B_s = 11.19 MeV 9740 1451 199 C_s = 0.01361 1/MeV 9740 1451 200 C_wiso = 23.5 MeV 9740 1451 201 r_s = 1.1803 fm 9740 1451 202 a_s = 0.601 fm 9740 1451 203 Spin-orbit: 9740 1451 204 V_so = 5.75 MeV 9740 1451 205 lambda_so = 0.005 1/MeV 9740 1451 206 W_so = -3.1 MeV 9740 1451 207 B_so = 160 MeV 9740 1451 208 r_so = 1.1214 fm 9740 1451 209 a_so = 0.59 fm 9740 1451 210 Coulomb: 9740 1451 211 C_coul = 1.3 9740 1451 212 r_c = 1.2452 fm 9740 1451 213 a_c = 0.545 fm 9740 1451 214 Deformation: 9740 1451 215 beta_2 = 0.213 9740 1451 216 beta_4 = 0.066 9740 1451 217 beta_6 = 0.0015 9740 1451 218 9740 1451 219 * Calculated strength function 9740 1451 220 S0= 0.94e-4 S1= 3.60e-4 R'= 9.05 fm (En=1 keV) 9740 1451 221 -------------------------------------------------- 9740 1451 222 9740 1451 223 Table 2. Level Scheme of Bk-245 9740 1451 224 ------------------- 9740 1451 225 No. Ex(MeV) J PI 9740 1451 226 ------------------- 9740 1451 227 0 0.00000 3/2 - * 9740 1451 228 1 0.02990 5/2 - * 9740 1451 229 2 0.04080 7/2 + 9740 1451 230 3 0.07160 7/2 - * 9740 1451 231 4 0.10180 9/2 + 9740 1451 232 5 0.12550 9/2 - * 9740 1451 233 ------------------- 9740 1451 234 *) Coupled levels in CC calculation 9740 1451 235 9740 1451 236 Table 3. Level density parameters 9740 1451 237 -------------------------------------------------------- 9740 1451 238 Nuclide a* Pair Eshell T E0 Ematch 9740 1451 239 1/MeV MeV MeV MeV MeV MeV 9740 1451 240 -------------------------------------------------------- 9740 1451 241 Bk-246 18.8984 0.0000 0.9401 0.2886 -0.6877 1.0000 9740 1451 242 Bk-245 18.8322 0.7667 1.2089 0.4136 -1.0946 3.2897 9740 1451 243 Bk-244 18.7661 0.0000 1.0000 0.2893 -0.6864 1.0000 9740 1451 244 Bk-243 18.6999 0.7698 1.1486 0.4243 -1.1853 3.4128 9740 1451 245 -------------------------------------------------------- 9740 1451 246 9740 1451 247 Table 4. Fission barrier parameters 9740 1451 248 ---------------------------------------- 9740 1451 249 Nuclide V_A hw_A V_B hw_B 9740 1451 250 MeV MeV MeV MeV 9740 1451 251 ---------------------------------------- 9740 1451 252 Bk-246 6.200 0.650 6.600 0.500 9740 1451 253 Bk-245 6.300 0.800 5.970 0.520 9740 1451 254 Bk-244 6.200 0.650 5.550 0.450 9740 1451 255 Bk-243 6.200 0.800 4.800 0.520 9740 1451 256 ---------------------------------------- 9740 1451 257 9740 1451 258 Table 5. Level density above inner saddle 9740 1451 259 -------------------------------------------------------- 9740 1451 260 Nuclide a* Pair Eshell T E0 Ematch 9740 1451 261 1/MeV MeV MeV MeV MeV MeV 9740 1451 262 -------------------------------------------------------- 9740 1451 263 Bk-246 21.1662 0.0000 2.6000 0.3230 -2.4113 2.0000 9740 1451 264 Bk-245 21.0921 0.8944 2.6000 0.2846 -0.9813 2.3944 9740 1451 265 Bk-244 21.0180 0.0000 2.6000 0.3242 -2.4113 2.0000 9740 1451 266 Bk-243 20.9439 0.8981 2.6000 0.3248 -1.5132 2.8981 9740 1451 267 -------------------------------------------------------- 9740 1451 268 9740 1451 269 Table 6. Level density above outer saddle 9740 1451 270 -------------------------------------------------------- 9740 1451 271 Nuclide a* Pair Eshell T E0 Ematch 9740 1451 272 1/MeV MeV MeV MeV MeV MeV 9740 1451 273 -------------------------------------------------------- 9740 1451 274 Bk-246 21.3551 0.0000 0.8400 0.3594 -1.7906 2.1000 9740 1451 275 Bk-245 24.4819 0.8944 0.8000 0.2888 -0.3662 2.3944 9740 1451 276 Bk-244 21.0180 0.0000 0.7600 0.3563 -1.7065 2.0000 9740 1451 277 Bk-243 20.9439 0.8981 0.7200 0.3575 -0.8078 2.8981 9740 1451 278 -------------------------------------------------------- 9740 1451 279 9740 1451 280 Table 7. Gamma-ray strength function for Bk-246 9740 1451 281 -------------------------------------------------------- 9740 1451 282 K0 = 1.500 E0 = 4.500 (MeV) 9740 1451 283 * E1: ER = 11.42 (MeV) EG = 2.72 (MeV) SIG = 249.84 (mb) 9740 1451 284 ER = 14.32 (MeV) EG = 4.20 (MeV) SIG = 499.67 (mb) 9740 1451 285 * M1: ER = 6.54 (MeV) EG = 4.00 (MeV) SIG = 1.77 (mb) 9740 1451 286 * E2: ER = 10.05 (MeV) EG = 3.16 (MeV) SIG = 7.21 (mb) 9740 1451 287 -------------------------------------------------------- 9740 1451 288 9740 1451 289 9740 1451 290 References 9740 1451 291 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9740 1451 292 2) R.J.Tuttle: INDC(NDS)-107/G+Special, p.29 (1979). 9740 1451 293 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 9740 1451 294 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 9740 1451 295 5) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9740 1451 296 6) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9740 1451 297 7) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9740 1451 298 8) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9740 1451 299 9) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9740 1451 300 Japanese. 9740 1451 301 10) C.Kalbach: Phys. Rev. C33, 818 (1986). 9740 1451 302 11) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9740 1451 303 12) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9740 1451 304 13) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9740 1451 305 14) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9740 1451 306 15) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9740 1451 307 16) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9740 1451 308 9740 1451 309 1 451 321 19740 1451 310 2 151 4 19740 1451 311 3 4 27 19740 1451 312 3 16 12 19740 1451 313 3 17 8 19740 1451 314 3 18 126 19740 1451 315 3 102 157 19740 1451 316 8 4 2 19740 1451 317 8 16 2 19740 1451 318 8 17 2 19740 1451 319 8 18 2 19740 1451 320 8 102 2 19740 1451 321 9740 1 099999 9740 0 0 0 9.724500+4 2.429610+2 0 0 1 09740 2151 1 9.724500+4 1.000000+0 0 0 1 09740 2151 2 1.000000-5 3.000000-1 0 0 0 09740 2151 3 1.500000+0 9.049000-1 0 0 0 09740 2151 4 9740 2 099999 9740 0 0 0 9.724500+4 2.429610+2 0 0 0 09740 3 4 1 0.000000+0-2.990000+4 0 0 1 729740 3 4 2 72 2 9740 3 4 3 3.002310+4 0.000000+0 4.096790+4 1.564690-1 5.000000+4 2.974251-19740 3 4 4 7.000000+4 5.051560-1 7.189470+4 5.217710-1 1.000000+5 8.054928-19740 3 4 5 1.019440+5 8.206796-1 1.022190+5 8.228339-1 1.200000+5 9.517023-19740 3 4 6 1.260160+5 9.917214-1 1.260170+5 9.917270-1 1.400000+5 1.078955+09740 3 4 7 1.700000+5 1.243906+0 2.000000+5 1.393153+0 2.500000+5 1.686302+09740 3 4 8 3.000000+5 1.791304+0 4.000000+5 2.125919+0 5.000000+5 2.463141+09740 3 4 9 6.000000+5 2.609557+0 7.000000+5 2.675470+0 8.000000+5 2.637356+09740 3 4 10 9.000000+5 2.610697+0 1.000000+6 2.614881+0 1.100000+6 2.622255+09740 3 4 11 1.200000+6 2.636214+0 1.300000+6 2.650687+0 1.400000+6 2.666863+09740 3 4 12 1.500000+6 2.673630+0 1.600000+6 2.678382+0 1.700000+6 2.671385+09740 3 4 13 1.800000+6 2.661294+0 1.900000+6 2.640686+0 2.000000+6 2.616948+09740 3 4 14 2.100000+6 2.585851+0 2.300000+6 2.514266+0 2.500000+6 2.433337+09740 3 4 15 2.700000+6 2.348868+0 3.000000+6 2.225996+0 3.500000+6 2.058795+09740 3 4 16 4.000000+6 1.958384+0 4.500000+6 1.901639+0 5.000000+6 1.870041+09740 3 4 17 5.500000+6 1.857699+0 6.000000+6 1.842231+0 6.500000+6 1.681993+09740 3 4 18 7.000000+6 1.403973+0 7.500000+6 1.138793+0 8.000000+6 9.210555-19740 3 4 19 8.500000+6 7.600239-1 9.000000+6 6.482911-1 9.500000+6 5.726701-19740 3 4 20 1.000000+7 5.211256-1 1.050000+7 4.845087-1 1.100000+7 4.573561-19740 3 4 21 1.150000+7 4.358341-1 1.200000+7 4.173530-1 1.250000+7 4.010870-19740 3 4 22 1.300000+7 3.861719-1 1.350000+7 3.722151-1 1.400000+7 3.590333-19740 3 4 23 1.450000+7 3.465243-1 1.500000+7 3.346438-1 1.550000+7 3.237712-19740 3 4 24 1.600000+7 3.128306-1 1.650000+7 3.031047-1 1.700000+7 2.934950-19740 3 4 25 1.750000+7 2.848403-1 1.800000+7 2.763107-1 1.850000+7 2.686291-19740 3 4 26 1.900000+7 2.610774-1 1.950000+7 2.542568-1 2.000000+7 2.475572-19740 3 4 27 9740 3 099999 9.724500+4 2.429610+2 0 0 0 09740 3 16 1 -6.971370+6-6.971370+6 0 0 1 279740 3 16 2 27 2 9740 3 16 3 7.000060+6 0.000000+0 7.500000+6 9.561510-3 8.000000+6 7.126850-29740 3 16 4 8.500000+6 1.534390-1 9.000000+6 2.220800-1 9.500000+6 2.669200-19740 3 16 5 1.000000+7 2.904150-1 1.050000+7 3.006750-1 1.100000+7 2.984840-19740 3 16 6 1.150000+7 2.896880-1 1.200000+7 2.818950-1 1.250000+7 2.711550-19740 3 16 7 1.300000+7 2.596610-1 1.350000+7 2.439830-1 1.400000+7 2.215580-19740 3 16 8 1.450000+7 1.949180-1 1.500000+7 1.683200-1 1.550000+7 1.429710-19740 3 16 9 1.600000+7 1.237120-1 1.650000+7 1.073700-1 1.700000+7 9.491710-29740 3 16 10 1.750000+7 8.565450-2 1.800000+7 7.871330-2 1.850000+7 7.356280-29740 3 16 11 1.900000+7 6.962310-2 1.950000+7 6.658740-2 2.000000+7 6.413800-29740 3 16 12 9740 3 099999 9.724500+4 2.429610+2 0 0 0 09740 3 17 1 -1.301840+7-1.301840+7 0 0 1 159740 3 17 2 15 2 9740 3 17 3 1.307190+7 0.000000+0 1.350000+7 4.571130-6 1.400000+7 1.907790-49740 3 17 4 1.450000+7 7.912450-4 1.500000+7 1.873810-3 1.550000+7 3.302480-39740 3 17 5 1.600000+7 3.983780-3 1.650000+7 5.331510-3 1.700000+7 5.678720-39740 3 17 6 1.750000+7 5.929260-3 1.800000+7 6.102110-3 1.850000+7 6.252270-39740 3 17 7 1.900000+7 6.408130-3 1.950000+7 6.589620-3 2.000000+7 6.765830-39740 3 17 8 9740 3 099999 9.724500+4 2.429610+2 0 0 0 09740 3 18 1 2.075000+8 2.075000+8 0 0 1 3679740 3 18 2 367 2 9740 3 18 3 1.000000-5 1.486945+2 1.103037-5 1.415762+2 1.216691-5 1.347984+29740 3 18 4 1.342055-5 1.283447+2 1.480336-5 1.221997+2 1.632865-5 1.163486+29740 3 18 5 1.801111-5 1.107773+2 1.986691-5 1.054724+2 2.191394-5 1.004212+29740 3 18 6 2.417189-5 9.561156+1 2.666248-5 9.103185+1 2.940971-5 8.667109+19740 3 18 7 3.243999-5 8.251881+1 3.578251-5 7.856503+1 3.946943-5 7.480024+19740 3 18 8 4.353624-5 7.121541+1 4.802208-5 6.780193+1 5.297013-5 6.455159+19740 3 18 9 5.842801-5 6.145659+1 6.444825-5 5.850951+1 7.108881-5 5.570327+19740 3 18 10 7.841358-5 5.303114+1 8.649308-5 5.048671+1 9.540506-5 4.806389+19740 3 18 11 1.052353-4 4.575687+1 1.160784-4 4.356013+1 1.280388-4 4.146840+19740 3 18 12 1.412315-4 3.947668+1 1.557836-4 3.758021+1 1.718351-4 3.577445+19740 3 18 13 1.895404-4 3.405508+1 2.090701-4 3.241801+1 2.306120-4 3.085931+19740 3 18 14 2.543736-4 2.937526+1 2.805835-4 2.796231+1 3.094939-4 2.661709+19740 3 18 15 3.413832-4 2.533637+1 3.765583-4 2.411709+1 4.153577-4 2.295634+19740 3 18 16 4.581549-4 2.185131+1 5.053618-4 2.079935+1 5.574328-4 1.979795+19740 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