JENDL-5 (Neutron sublibrary (activation cs)) Ru-105 0 0 0 0 4.410500+4 1.040065+2 0 0 6 14452 1451 1 0.000000+0 1.000000+0 0 0 0 64452 1451 2 1.000000+0 2.000000+7 0 0 10 54452 1451 3 2.936000+2 0.000000+0 4 0 390 264452 1451 4 44-Ru-105 JAEA EVAL-JUL12 K.Shibata 4452 1451 5 JNST 50, 1177 (2013) DIST-DEC21 20180517 4452 1451 6 ----JENDL-5 MATERIAL 4452 4452 1451 7 -----INCIDENT NEUTRON DATA 4452 1451 8 ------ENDF-6 FORMAT 4452 1451 9 4452 1451 10 History 4452 1451 11 12-07 The fast neutron cross sections were re-evaluated by 4452 1451 12 K. Shibata (JAEA) /1/ using the POD code. 4452 1451 13 18-05 Only decay data added by K.Shibata. 4452 1451 14 21-11 revised by O.Iwamoto 4452 1451 15 (MF8/MT4) added 4452 1451 16 21-11 above 20 MeV, JENDL/ImPACT-2018 merged by O.Iwamoto 4452 1451 17 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 4452 1451 18 4452 1451 19 4452 1451 20 MF= 1 General information 4452 1451 21 MT=451 Descriptive data and directory 4452 1451 22 4452 1451 23 MF= 2 Resonance parameters 4452 1451 24 MT=151 Resolved and unresolved resonance parameters 4452 1451 25 No resolved resonance parameters are given. 4452 1451 26 The 1/v-shped capture cross section is assumed below 12 eV. 4452 1451 27 At 0.0253 eV, the cross section was normalized to the value 4452 1451 28 of 0.39 b. 4452 1451 29 Constant elastic scattering cross sections of 5.31 b were 4452 1451 30 given below 12 eV. 4452 1451 31 Unresolved resonance region: 12 eV - 120 keV 4452 1451 32 The parameters were obtained by fitting to the total and 4452 1451 33 capture cross sections calculated from POD /2/. The 4452 1451 34 unresolved parameters should be used only for self-shielding4452 1451 35 calculation. 4452 1451 36 4452 1451 37 Thermal cross sections and resonance integrals at 300 K 4452 1451 38 ---------------------------------------------------------- 4452 1451 39 0.0253 eV res. integ. (*) 4452 1451 40 (barns) (barns) 4452 1451 41 ---------------------------------------------------------- 4452 1451 42 Total 5.7313E+00 4452 1451 43 Elastic 5.3362E+00 4452 1451 44 n,gamma 3.9018E-01 1.1742E+02 4452 1451 45 ---------------------------------------------------------- 4452 1451 46 (*) Integrated from 0.5 eV to 10 MeV. 4452 1451 47 4452 1451 48 MF= 3 Neutron cross sections 4452 1451 49 MT= 1 Total cross section 4452 1451 50 Calculated with POD code /2/. 4452 1451 51 4452 1451 52 MT= 2 Elastic scattering cross section 4452 1451 53 The cross section was obtaned by subtracting the non-elastic 4452 1451 54 cross section from the total cross section. 4452 1451 55 4452 1451 56 MT= 3 Non-elastic cross section 4452 1451 57 Sum of partial non-elastic cross sections. 4452 1451 58 4452 1451 59 MT= 4,51-91 (n,n') cross section 4452 1451 60 Calculated with POD code /2/. 4452 1451 61 4452 1451 62 MT= 16 (n,2n) cross section 4452 1451 63 Calculated with POD code /2/. 4452 1451 64 4452 1451 65 MT= 17 (n,3n) cross section 4452 1451 66 Calculated with POD code /2/. 4452 1451 67 4452 1451 68 MT= 22 (n,na) cross section 4452 1451 69 Calculated with POD code /2/. 4452 1451 70 4452 1451 71 MT= 28 (n,np) cross section 4452 1451 72 Calculated with POD code /2/. 4452 1451 73 4452 1451 74 MT= 32 (n,nd) cross section 4452 1451 75 Calculated with POD code /2/. 4452 1451 76 4452 1451 77 MT=102 Capture cross section 4452 1451 78 Calculated with POD code /2/. 4452 1451 79 4452 1451 80 MT=103 (n,p) cross section 4452 1451 81 Calculated with POD code /2/. 4452 1451 82 4452 1451 83 MT=104 (n,d) cross section 4452 1451 84 Calculated with POD code /2/. 4452 1451 85 4452 1451 86 MT=105 (n,t) cross section 4452 1451 87 Calculated with POD code /2/. 4452 1451 88 4452 1451 89 MT=106 (n,He3) cross section 4452 1451 90 Calculated with POD code /2/. 4452 1451 91 4452 1451 92 MT=107 (n,a) cross section 4452 1451 93 Calculated with POD code /2/. 4452 1451 94 4452 1451 95 MT=203 (n,xp) cross section 4452 1451 96 Calculated with POD code /2/. 4452 1451 97 4452 1451 98 MT=204 (n,xd) cross section 4452 1451 99 Calculated with POD code /2/. 4452 1451 100 4452 1451 101 MT=205 (n,xt) cross section 4452 1451 102 Calculated with POD code /2/. 4452 1451 103 4452 1451 104 MT=206 (n,xHe3) cross section 4452 1451 105 Calculated with POD code /2/. 4452 1451 106 4452 1451 107 MT=207 (n,xa) cross section 4452 1451 108 Calculated with POD code /2/. 4452 1451 109 4452 1451 110 MF= 4 Angular distributions of emitted neutrons 4452 1451 111 MT= 2 Elastic scattering 4452 1451 112 Calculated with POD code /2/. 4452 1451 113 4452 1451 114 MF= 6 Energy-angle distributions of emitted particles 4452 1451 115 MT= 16 (n,2n) reaction 4452 1451 116 Neutron spectra calculated with POD/2/. 4452 1451 117 4452 1451 118 MT= 17 (n,3n) reaction 4452 1451 119 Neutron spectra calculated with POD/2/. 4452 1451 120 4452 1451 121 MT= 22 (n,na) reaction 4452 1451 122 Neutron spectra calculated with POD/2/. 4452 1451 123 4452 1451 124 MT= 28 (n,np) reaction 4452 1451 125 Neutron spectra calculated with POD/2/. 4452 1451 126 4452 1451 127 MT= 32 (n,nd) reaction 4452 1451 128 Neutron spectra calculated with POD/2/. 4452 1451 129 4452 1451 130 MT= 51 (n,n') reaction 4452 1451 131 Neutron angular distributions calculated with POD/2/. 4452 1451 132 4452 1451 133 MT= 52 (n,n') reaction 4452 1451 134 Neutron angular distributions calculated with POD/2/. 4452 1451 135 4452 1451 136 MT= 53 (n,n') reaction 4452 1451 137 Neutron angular distributions calculated with POD/2/. 4452 1451 138 4452 1451 139 MT= 54 (n,n') reaction 4452 1451 140 Neutron angular distributions calculated with POD/2/. 4452 1451 141 4452 1451 142 MT= 55 (n,n') reaction 4452 1451 143 Neutron angular distributions calculated with POD/2/. 4452 1451 144 4452 1451 145 MT= 56 (n,n') reaction 4452 1451 146 Neutron angular distributions calculated with POD/2/. 4452 1451 147 4452 1451 148 MT= 57 (n,n') reaction 4452 1451 149 Neutron angular distributions calculated with POD/2/. 4452 1451 150 4452 1451 151 MT= 58 (n,n') reaction 4452 1451 152 Neutron angular distributions calculated with POD/2/. 4452 1451 153 4452 1451 154 MT= 59 (n,n') reaction 4452 1451 155 Neutron angular distributions calculated with POD/2/. 4452 1451 156 4452 1451 157 MT= 60 (n,n') reaction 4452 1451 158 Neutron angular distributions calculated with POD/2/. 4452 1451 159 4452 1451 160 MT= 61 (n,n') reaction 4452 1451 161 Neutron angular distributions calculated with POD/2/. 4452 1451 162 4452 1451 163 MT= 62 (n,n') reaction 4452 1451 164 Neutron angular distributions calculated with POD/2/. 4452 1451 165 4452 1451 166 MT= 63 (n,n') reaction 4452 1451 167 Neutron angular distributions calculated with POD/2/. 4452 1451 168 4452 1451 169 MT= 64 (n,n') reaction 4452 1451 170 Neutron angular distributions calculated with POD/2/. 4452 1451 171 4452 1451 172 MT= 65 (n,n') reaction 4452 1451 173 Neutron angular distributions calculated with POD/2/. 4452 1451 174 4452 1451 175 MT= 66 (n,n') reaction 4452 1451 176 Neutron angular distributions calculated with POD/2/. 4452 1451 177 4452 1451 178 MT= 67 (n,n') reaction 4452 1451 179 Neutron angular distributions calculated with POD/2/. 4452 1451 180 4452 1451 181 MT= 68 (n,n') reaction 4452 1451 182 Neutron angular distributions calculated with POD/2/. 4452 1451 183 4452 1451 184 MT= 69 (n,n') reaction 4452 1451 185 Neutron angular distributions calculated with POD/2/. 4452 1451 186 4452 1451 187 MT= 70 (n,n') reaction 4452 1451 188 Neutron angular distributions calculated with POD/2/. 4452 1451 189 4452 1451 190 MT= 71 (n,n') reaction 4452 1451 191 Neutron angular distributions calculated with POD/2/. 4452 1451 192 4452 1451 193 MT= 72 (n,n') reaction 4452 1451 194 Neutron angular distributions calculated with POD/2/. 4452 1451 195 4452 1451 196 MT= 73 (n,n') reaction 4452 1451 197 Neutron angular distributions calculated with POD/2/. 4452 1451 198 4452 1451 199 MT= 74 (n,n') reaction 4452 1451 200 Neutron angular distributions calculated with POD/2/. 4452 1451 201 4452 1451 202 MT= 75 (n,n') reaction 4452 1451 203 Neutron angular distributions calculated with POD/2/. 4452 1451 204 4452 1451 205 MT= 76 (n,n') reaction 4452 1451 206 Neutron angular distributions calculated with POD/2/. 4452 1451 207 4452 1451 208 MT= 77 (n,n') reaction 4452 1451 209 Neutron angular distributions calculated with POD/2/. 4452 1451 210 4452 1451 211 MT= 78 (n,n') reaction 4452 1451 212 Neutron angular distributions calculated with POD/2/. 4452 1451 213 4452 1451 214 MT= 79 (n,n') reaction 4452 1451 215 Neutron angular distributions calculated with POD/2/. 4452 1451 216 4452 1451 217 MT= 80 (n,n') reaction 4452 1451 218 Neutron angular distributions calculated with POD/2/. 4452 1451 219 4452 1451 220 MT= 81 (n,n') reaction 4452 1451 221 Neutron angular distributions calculated with POD/2/. 4452 1451 222 4452 1451 223 MT= 82 (n,n') reaction 4452 1451 224 Neutron angular distributions calculated with POD/2/. 4452 1451 225 4452 1451 226 MT= 91 (n,n') reaction 4452 1451 227 Neutron spectra calculated with POD/2/. 4452 1451 228 4452 1451 229 MT= 203 (n,xp) reaction 4452 1451 230 Proton spectra calculated with POD/2/. 4452 1451 231 4452 1451 232 MT= 204 (n,xd) reaction 4452 1451 233 Deuteron spectra calculated with POD/2/. 4452 1451 234 4452 1451 235 MT= 205 (n,xt) reaction 4452 1451 236 Triton spectra calculated with POD/2/. 4452 1451 237 4452 1451 238 MT= 206 (n,xHe3) reaction 4452 1451 239 He3 spectra calculated with POD/2/. 4452 1451 240 4452 1451 241 MT= 207 (n,xa) reaction 4452 1451 242 Alpha spectra calculated with POD/2/. 4452 1451 243 4452 1451 244 MF= 8 Information on decay data 4452 1451 245 MT= 16 (n,2n) reaction 4452 1451 246 4452 1451 247 MT= 17 (n,3n) reaction 4452 1451 248 4452 1451 249 MT= 22 (n,na) reaction 4452 1451 250 4452 1451 251 MT= 28 (n,np) reaction 4452 1451 252 4452 1451 253 MT= 32 (n,nd) reaction 4452 1451 254 4452 1451 255 MT=102 (n,g) reaction 4452 1451 256 4452 1451 257 MT=103 (n,p) reaction 4452 1451 258 4452 1451 259 MT=104 (n,d) reaction 4452 1451 260 4452 1451 261 MT=105 (n,t) reaction 4452 1451 262 4452 1451 263 MT=106 (n,He3) reaction 4452 1451 264 4452 1451 265 MT=107 (n,a) reaction 4452 1451 266 4452 1451 267 MF=12 Gamma-ray multiplicities 4452 1451 268 MT= 3 Non-elastic gamma emission 4452 1451 269 Calculated with POD code /2/. 4452 1451 270 4452 1451 271 MF=14 Gamma-ray angular distributions 4452 1451 272 MT= 3 Non-elastic gamma emission 4452 1451 273 Assumed to be isotropic. 4452 1451 274 4452 1451 275 MF=15 Gamma-ray spectra 4452 1451 276 MT= 3 Non-elastic gamma emission 4452 1451 277 Calculated with POD code /2/. 4452 1451 278 4452 1451 279 4452 1451 280 4452 1451 281 *************************************************************** 4452 1451 282 * Nuclear Model Calculations with POD Code /2/ * 4452 1451 283 *************************************************************** 4452 1451 284 1. Theoretical models 4452 1451 285 The POD code is based on the spherical optical model, the 4452 1451 286 distorted-wave Born approximaiton (DWBA), one-component exciton 4452 1451 287 preequilibrium model, and the Hauser-Feshbach-Moldauer statis- 4452 1451 288 tical model. With the preequilibrim model, semi-empirical 4452 1451 289 pickup and knockout process can be taken into account for 4452 1451 290 composite-particle emission. The gamma-ray emission from the 4452 1451 291 compound nucleus can be calculated within the framework of the 4452 1451 292 exciton model. The code is capable of reading in particle 4452 1451 293 transmission coefficients calculated by separate spherical or 4452 1451 294 coupled-channel optical model code. 4452 1451 295 4452 1451 296 2. Optical model parameters 4452 1451 297 Neutrons: 4452 1451 298 Coupled-channel optical model parameters /3/ 4452 1451 299 Protons: 4452 1451 300 Koning and Delaroche /4/ 4452 1451 301 Deuterons: 4452 1451 302 Lohr and Haeberli /5/ 4452 1451 303 Tritons: 4452 1451 304 Becchetti and Greenlees /6/ 4452 1451 305 He-3: 4452 1451 306 Becchetti and Greenlees /6/ 4452 1451 307 Alphas: 4452 1451 308 Lemos /7/ potentials modified by Arthur and Young /8/ 4452 1451 309 4452 1451 310 3. Level scheme of Ru-105 4452 1451 311 ------------------------- 4452 1451 312 No. Ex(MeV) J PI 4452 1451 313 ------------------------- 4452 1451 314 0 0.00000 3/2 + 4452 1451 315 1 0.02061 5/2 + 4452 1451 316 2* 0.10794 5/2 + 4452 1451 317 3 0.15952 1/2 + 4452 1451 318 4 0.16381 3/2 + 4452 1451 319 5 0.20860 11/2 - 4452 1451 320 6* 0.22948 7/2 + 4452 1451 321 7 0.24441 1/2 - 4452 1451 322 8 0.24637 5/2 - 4452 1451 323 9 0.27272 3/2 - 4452 1451 324 10 0.30168 7/2 + 4452 1451 325 11 0.32160 3/2 - 4452 1451 326 12 0.44195 5/2 + 4452 1451 327 13 0.46627 3/2 + 4452 1451 328 14 0.49089 3/2 - 4452 1451 329 15 0.57390 15/2 - 4452 1451 330 16 0.57800 5/2 - 4452 1451 331 17 0.57811 3/2 - 4452 1451 332 18 0.58212 5/2 + 4452 1451 333 19 0.62583 7/2 + 4452 1451 334 20 0.63127 1/2 + 4452 1451 335 21 0.64403 3/2 - 4452 1451 336 22 0.67080 3/2 - 4452 1451 337 23 0.72592 9/2 + 4452 1451 338 24 0.75671 3/2 + 4452 1451 339 25 0.78456 1/2 - 4452 1451 340 26 0.80577 1/2 + 4452 1451 341 27 0.82433 3/2 + 4452 1451 342 28 0.84112 7/2 + 4452 1451 343 29 0.87343 1/2 + 4452 1451 344 30 0.88657 3/2 + 4452 1451 345 31 0.90309 5/2 - 4452 1451 346 32 0.91400 5/2 + 4452 1451 347 ------------------------- 4452 1451 348 Levels above 0.92400 MeV are assumed to be continuous. 4452 1451 349 The symbol (*) stands for the excited level involved in the 4452 1451 350 coupled-channel calculation. 4452 1451 351 4452 1451 352 4. Level density parameters 4452 1451 353 Energy-dependent parameters of Mengoni-Nakajima /9/ were used 4452 1451 354 ---------------------------------------------------------- 4452 1451 355 Nuclei a* Pair Esh T E0 Ematch Elv_max 4452 1451 356 1/MeV MeV MeV MeV MeV MeV MeV 4452 1451 357 ---------------------------------------------------------- 4452 1451 358 Ru-106 13.487 2.331 4.166 0.658 0.033 8.035 1.392 4452 1451 359 Ru-105 14.068 1.171 4.250 0.657 -1.412 7.205 0.914 4452 1451 360 Ru-104 13.272 2.353 3.632 0.656 0.316 7.723 2.619 4452 1451 361 Ru-103 13.854 1.182 3.548 0.717 -1.842 8.034 0.954 4452 1451 362 Tc-105 12.819 1.171 4.913 0.743 -2.106 8.466 0.610 4452 1451 363 Tc-104 13.220 0.000 4.817 0.571 -1.464 4.245 0.399 4452 1451 364 Tc-103 12.611 1.182 4.679 0.684 -1.198 7.098 0.692 4452 1451 365 Mo-103 13.854 1.182 4.986 0.610 -0.985 6.470 0.746 4452 1451 366 Mo-102 13.056 2.376 4.689 0.670 -0.069 8.293 1.398 4452 1451 367 Mo-101 14.580 1.194 4.672 0.597 -1.025 6.467 0.984 4452 1451 368 ---------------------------------------------------------- 4452 1451 369 4452 1451 370 5. Gamma-ray strength functions 4452 1451 371 M1, E2: Standard Lorentzian (SLO) 4452 1451 372 E1 : Modified Lorentzian (MLO) /10/ 4452 1451 373 4452 1451 374 6. Preequilibrium process 4452 1451 375 Preequilibrium is on for n, p, d, t, He-3, and alpha. 4452 1451 376 Preequilibrium capture is on. 4452 1451 377 4452 1451 378 References 4452 1451 379 1) K.Shibata, J. Nucl. Sci. Technol., 50, 1177 (2013). 4452 1451 380 2) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 4452 1451 381 3) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 4452 1451 382 4) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 4452 1451 383 5) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 4452 1451 384 6) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization 4452 1451 385 Phenomena in Nuclear Reactions," p.682, The University 4452 1451 386 of Wisconsin Press (1971). 4452 1451 387 7) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 4452 1451 388 8) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 4452 1451 389 9) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 4452 1451 390 (1994). 4452 1451 391 10) V.A.Plujko et al., J. Nucl. Sci. Technol. Suppl. 2, 811 4452 1451 392 (2002). 4452 1451 393 4452 1451 394 1 451 420 14452 1451 395 2 151 4 14452 1451 396 3 4 31 14452 1451 397 3 16 10 14452 1451 398 3 17 6 14452 1451 399 3 22 7 14452 1451 400 3 28 7 14452 1451 401 3 32 5 14452 1451 402 3 102 133 14452 1451 403 3 103 11 14452 1451 404 3 104 7 14452 1451 405 3 105 8 14452 1451 406 3 106 5 14452 1451 407 3 107 12 14452 1451 408 8 4 2 14452 1451 409 8 16 2 14452 1451 410 8 17 2 14452 1451 411 8 22 2 14452 1451 412 8 28 2 14452 1451 413 8 32 2 14452 1451 414 8 102 2 14452 1451 415 8 103 2 14452 1451 416 8 104 2 14452 1451 417 8 105 2 14452 1451 418 8 106 2 14452 1451 419 8 107 2 14452 1451 420 4452 1 099999 4452 0 0 0 4.410500+4 1.040065+2 0 0 1 04452 2151 1 4.410500+4 1.000000+0 0 0 1 04452 2151 2 1.200000+1 1.200000+5 0 0 0 04452 2151 3 1.500000+0 5.222500-1 0 0 0 04452 2151 4 4452 2 099999 4452 0 0 0 4.410500+4 1.040065+2 0 0 0 04452 3 4 1 0.000000+0-2.061000+4 0 0 1 824452 3 4 2 82 2 4452 3 4 3 2.080816+4 0.000000+0 2.100000+4 0.000000+0 2.500000+4 1.887000-14452 3 4 4 3.000000+4 2.426000-1 4.000000+4 3.128000-1 5.000000+4 3.638000-14452 3 4 5 6.000000+4 4.059000-1 7.000000+4 4.418000-1 8.000000+4 4.736000-14452 3 4 6 9.000000+4 5.023000-1 1.000000+5 5.287000-1 1.089748+5 5.340041-14452 3 4 7 1.610517+5 7.449978-1 1.653900+5 7.715982-1 2.000000+5 1.125810+04452 3 4 8 2.106056+5 1.149247+0 2.316864+5 1.197594+0 2.467599+5 1.250376+04452 3 4 9 2.487418+5 1.259667+0 2.753442+5 1.440694+0 3.000000+5 1.665994+04452 3 4 10 3.045806+5 1.675532+0 3.246871+5 1.730969+0 4.000000+5 2.017180+04452 3 4 11 4.461993+5 2.067209+0 4.707531+5 2.111127+0 4.956098+5 2.175568+04452 3 4 12 5.000000+5 2.196793+0 5.794179+5 2.263986+0 5.835573+5 2.267489+04452 3 4 13 5.836684+5 2.267684+0 5.877170+5 2.277982+0 6.000000+5 2.316302+04452 3 4 14 6.318472+5 2.322785+0 6.373395+5 2.325511+0 6.502222+5 2.334634+04452 3 4 15 6.772496+5 2.364466+0 7.000000+5 2.401108+0 7.328996+5 2.410602+04452 3 4 16 7.639856+5 2.423711+0 7.921034+5 2.443836+0 8.000000+5 2.452631+04452 3 4 17 8.135173+5 2.452129+0 8.322558+5 2.453856+0 8.492072+5 2.459367+04452 3 4 18 8.818278+5 2.476498+0 8.950942+5 2.485039+0 9.000000+5 2.489956+04452 3 4 19 9.117730+5 2.501572+0 9.227879+5 2.514707+0 9.328841+5 2.528689+04452 3 4 20 1.000000+6 2.621866+0 1.250000+6 2.632468+0 1.500000+6 2.633960+04452 3 4 21 2.000000+6 2.640019+0 2.500000+6 2.611826+0 3.000000+6 2.559277+04452 3 4 22 3.500000+6 2.497772+0 4.000000+6 2.438646+0 4.500000+6 2.387246+04452 3 4 23 5.000000+6 2.343048+0 5.500000+6 2.305350+0 6.000000+6 2.270738+04452 3 4 24 6.500000+6 2.174013+0 7.000000+6 1.846660+0 7.500000+6 1.474614+04452 3 4 25 8.000000+6 1.144055+0 8.500000+6 9.187977-1 9.000000+6 7.549392-14452 3 4 26 9.500000+6 6.497530-1 1.000000+7 5.745963-1 1.100000+7 4.830982-14452 3 4 27 1.200000+7 4.246521-1 1.300000+7 3.823395-1 1.400000+7 3.517003-14452 3 4 28 1.450000+7 3.377335-1 1.500000+7 3.262522-1 1.600000+7 3.047108-14452 3 4 29 1.700000+7 2.861194-1 1.800000+7 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