JENDL-5 (Neutron sublibrary (activation cs)) Kr- 82 0 0 0 0 3.608200+4 8.120981+1 0 0 6 13637 1451 1 0.000000+0 0.000000+0 0 0 0 63637 1451 2 1.000000+0 2.000000+7 0 0 10 53637 1451 3 2.936000+2 0.000000+0 4 0 345 243637 1451 4 36-Kr- 82 JAEA EVAL-AUG09 K.Shibata, A.Ichihara, S.Kunieda 3637 1451 5 DIST-DEC21 20091118 3637 1451 6 ----JENDL-5 MATERIAL 3637 3637 1451 7 -----INCIDENT NEUTRON DATA 3637 1451 8 ------ENDF-6 FORMAT 3637 1451 9 3637 1451 10 History 3637 1451 11 09-08 Evaluated by K. Shibata, A. Ichihara and S. Kunieda. 3637 1451 12 09-10 Compiled by K. Shibata. 3637 1451 13 21-11 revised by O.Iwamoto 3637 1451 14 (MF8/MT4,16,17,22,28,102-107) added 3637 1451 15 21-11 above 20 MeV, JENDL/ImPACT-2018 merged by O.Iwamoto 3637 1451 16 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 3637 1451 17 3637 1451 18 3637 1451 19 MF= 1 General information 3637 1451 20 MT=451 Descriptive data and directory 3637 1451 21 3637 1451 22 MF= 2 Resonance parameters 3637 1451 23 MT=151 Resolved and unresolved resonance parameters 3637 1451 24 Resolved resonance region (MLBW formula) : below 0.4 keV 3637 1451 25 Resonance parameters were based on Mughabghab et al./1/ 3637 1451 26 The resonance level at 1.55 keV was abandoned, because this 3637 1451 27 level belongs possibly to Kr-83. Neutron widths of the 3637 1451 28 resonance levels from 646 to 1659 eV were derived from the 3637 1451 29 reduced neutron width (19.7 meV) of the 1st level and the 3637 1451 30 resonance energy of each level. Average radiation width of 3637 1451 31 230 meV given by Mughabghab et al. was adopted for all 3637 1451 32 resonance levels including a negative resonance, and was 3637 1451 33 slightly modified to 227 meV so as to reproduce the thermal 3637 1451 34 capture cross section of 28+-20 barns given by Mughabghab et3637 1451 35 al. The values of neutron orbital angular momentum L and 3637 1451 36 total spin J were assumed to be 0 and 0.5 for all resonance 3637 1451 37 levels, respectively. Scattering radius was also taken from3637 1451 38 the graph (fig. 1, Part A) given by Mughabghab et al. 3637 1451 39 In JENDL-4, the radiation width of the negative resonance 3637 1451 40 was adjusted so as to reproduce the thermal capture cross 3637 1451 41 section recommended by Mughabghab /2/. 3637 1451 42 3637 1451 43 Unresolved resonance region: 0.4 keV - 1 MeV 3637 1451 44 The parameters were obtained by fitting to the total and 3637 1451 45 capture cross sections calculated from POD /3/. The 3637 1451 46 unresolved parameters should be used only for self-shielding3637 1451 47 calculation. 3637 1451 48 3637 1451 49 Thermal cross sections and resonance integrals at 300 K 3637 1451 50 ---------------------------------------------------------- 3637 1451 51 0.0253 eV res. integ. (*) 3637 1451 52 (barns) (barns) 3637 1451 53 ---------------------------------------------------------- 3637 1451 54 Total 3.7655E+01 3637 1451 55 Elastic 1.8579E+01 3637 1451 56 n,gamma 1.9076E+01 2.2434E+02 3637 1451 57 ---------------------------------------------------------- 3637 1451 58 (*) Integrated from 0.5 eV to 10 MeV. 3637 1451 59 3637 1451 60 MF= 3 Neutron cross sections 3637 1451 61 MT= 1 Total cross section 3637 1451 62 Calculated with POD code /3/. 3637 1451 63 3637 1451 64 MT= 2 Elastic scattering cross section 3637 1451 65 Obtained by subtracting non-elastic cross sections from total 3637 1451 66 cross sections. 3637 1451 67 3637 1451 68 MT= 3 Non-elastic cross section 3637 1451 69 Sum of partial non-elastic cross sections. 3637 1451 70 3637 1451 71 MT= 4,51-91 (n,n') cross section 3637 1451 72 Calculated with POD code /3/. 3637 1451 73 3637 1451 74 MT= 16 (n,2n) cross section 3637 1451 75 Calculated with POD code /3/. 3637 1451 76 3637 1451 77 MT= 17 (n,3n) cross section 3637 1451 78 Calculated with POD code /3/. 3637 1451 79 3637 1451 80 MT= 22 (n,na) cross section 3637 1451 81 Calculated with POD code /3/. 3637 1451 82 3637 1451 83 MT= 28 (n,np) cross section 3637 1451 84 Calculated with POD code /3/. 3637 1451 85 3637 1451 86 MT=102 Capture cross section 3637 1451 87 Calculated with POD code /3/. 3637 1451 88 3637 1451 89 MT=103 (n,p) cross section 3637 1451 90 Calculated with POD code /3/. 3637 1451 91 3637 1451 92 MT=104 (n,d) cross section 3637 1451 93 Calculated with POD code /3/. 3637 1451 94 3637 1451 95 MT=105 (n,t) cross section 3637 1451 96 Calculated with POD code /3/. 3637 1451 97 3637 1451 98 MT=106 (n,He3) cross section 3637 1451 99 Calculated with POD code /3/. 3637 1451 100 3637 1451 101 MT=107 (n,a) cross section 3637 1451 102 Calculated with POD code /3/. 3637 1451 103 3637 1451 104 MT=203 (n,xp) cross section 3637 1451 105 Calculated with POD code /3/. 3637 1451 106 3637 1451 107 MT=204 (n,xd) cross section 3637 1451 108 Calculated with POD code /3/. 3637 1451 109 3637 1451 110 MT=205 (n,xt) cross section 3637 1451 111 Calculated with POD code /3/. 3637 1451 112 3637 1451 113 MT=206 (n,xHe3) cross section 3637 1451 114 Calculated with POD code /3/. 3637 1451 115 3637 1451 116 MT=207 (n,xa) cross section 3637 1451 117 Calculated with POD code /3/. 3637 1451 118 3637 1451 119 MF= 4 Angular distributions of emitted neutrons 3637 1451 120 MT= 2 Elastic scattering 3637 1451 121 Calculated with POD code /3/. 3637 1451 122 3637 1451 123 MF= 6 Energy-angle distributions of emitted particles 3637 1451 124 MT= 16 (n,2n) reaction 3637 1451 125 Neutron spectra calculated with POD/3/. 3637 1451 126 3637 1451 127 MT= 17 (n,3n) reaction 3637 1451 128 Neutron spectra calculated with POD/3/. 3637 1451 129 3637 1451 130 MT= 22 (n,na) reaction 3637 1451 131 Neutron spectra calculated with POD/3/. 3637 1451 132 3637 1451 133 MT= 28 (n,np) reaction 3637 1451 134 Neutron spectra calculated with POD/3/. 3637 1451 135 3637 1451 136 MT= 51 (n,n') reaction 3637 1451 137 Neutron angular distributions calculated with POD/3/. 3637 1451 138 3637 1451 139 MT= 52 (n,n') reaction 3637 1451 140 Neutron angular distributions calculated with POD/3/. 3637 1451 141 3637 1451 142 MT= 53 (n,n') reaction 3637 1451 143 Neutron angular distributions calculated with POD/3/. 3637 1451 144 3637 1451 145 MT= 54 (n,n') reaction 3637 1451 146 Neutron angular distributions calculated with POD/3/. 3637 1451 147 3637 1451 148 MT= 55 (n,n') reaction 3637 1451 149 Neutron angular distributions calculated with POD/3/. 3637 1451 150 3637 1451 151 MT= 56 (n,n') reaction 3637 1451 152 Neutron angular distributions calculated with POD/3/. 3637 1451 153 3637 1451 154 MT= 57 (n,n') reaction 3637 1451 155 Neutron angular distributions calculated with POD/3/. 3637 1451 156 3637 1451 157 MT= 58 (n,n') reaction 3637 1451 158 Neutron angular distributions calculated with POD/3/. 3637 1451 159 3637 1451 160 MT= 59 (n,n') reaction 3637 1451 161 Neutron angular distributions calculated with POD/3/. 3637 1451 162 3637 1451 163 MT= 60 (n,n') reaction 3637 1451 164 Neutron angular distributions calculated with POD/3/. 3637 1451 165 3637 1451 166 MT= 61 (n,n') reaction 3637 1451 167 Neutron angular distributions calculated with POD/3/. 3637 1451 168 3637 1451 169 MT= 62 (n,n') reaction 3637 1451 170 Neutron angular distributions calculated with POD/3/. 3637 1451 171 3637 1451 172 MT= 63 (n,n') reaction 3637 1451 173 Neutron angular distributions calculated with POD/3/. 3637 1451 174 3637 1451 175 MT= 64 (n,n') reaction 3637 1451 176 Neutron angular distributions calculated with POD/3/. 3637 1451 177 3637 1451 178 MT= 65 (n,n') reaction 3637 1451 179 Neutron angular distributions calculated with POD/3/. 3637 1451 180 3637 1451 181 MT= 66 (n,n') reaction 3637 1451 182 Neutron angular distributions calculated with POD/3/. 3637 1451 183 3637 1451 184 MT= 67 (n,n') reaction 3637 1451 185 Neutron angular distributions calculated with POD/3/. 3637 1451 186 3637 1451 187 MT= 68 (n,n') reaction 3637 1451 188 Neutron angular distributions calculated with POD/3/. 3637 1451 189 3637 1451 190 MT= 69 (n,n') reaction 3637 1451 191 Neutron angular distributions calculated with POD/3/. 3637 1451 192 3637 1451 193 MT= 70 (n,n') reaction 3637 1451 194 Neutron angular distributions calculated with POD/3/. 3637 1451 195 3637 1451 196 MT= 71 (n,n') reaction 3637 1451 197 Neutron angular distributions calculated with POD/3/. 3637 1451 198 3637 1451 199 MT= 72 (n,n') reaction 3637 1451 200 Neutron angular distributions calculated with POD/3/. 3637 1451 201 3637 1451 202 MT= 73 (n,n') reaction 3637 1451 203 Neutron angular distributions calculated with POD/3/. 3637 1451 204 3637 1451 205 MT= 74 (n,n') reaction 3637 1451 206 Neutron angular distributions calculated with POD/3/. 3637 1451 207 3637 1451 208 MT= 75 (n,n') reaction 3637 1451 209 Neutron angular distributions calculated with POD/3/. 3637 1451 210 3637 1451 211 MT= 91 (n,n') reaction 3637 1451 212 Neutron spectra calculated with POD/3/. 3637 1451 213 3637 1451 214 MT= 203 (n,xp) reaction 3637 1451 215 Proton spectra calculated with POD/3/. 3637 1451 216 3637 1451 217 MT= 204 (n,xd) reaction 3637 1451 218 Deuteron spectra calculated with POD/3/. 3637 1451 219 3637 1451 220 MT= 205 (n,xt) reaction 3637 1451 221 Triton spectra calculated with POD/3/. 3637 1451 222 3637 1451 223 MT= 206 (n,xHe3) reaction 3637 1451 224 He3 spectra calculated with POD/3/. 3637 1451 225 3637 1451 226 MT= 207 (n,xa) reaction 3637 1451 227 Alpha spectra calculated with POD/3/. 3637 1451 228 3637 1451 229 MF=12 Gamma-ray multiplicities 3637 1451 230 MT= 3 Non-elastic gamma emission 3637 1451 231 Calculated with POD code /3/. 3637 1451 232 3637 1451 233 MF=14 Gamma-ray angular distributions 3637 1451 234 MT= 3 Non-elastic gamma emission 3637 1451 235 Assumed to be isotropic. 3637 1451 236 3637 1451 237 MF=15 Gamma-ray spectra 3637 1451 238 MT= 3 Non-elastic gamma emission 3637 1451 239 Calculated with POD code /3/. 3637 1451 240 3637 1451 241 3637 1451 242 3637 1451 243 *************************************************************** 3637 1451 244 * Nuclear Model Calculations with POD Code /3/ * 3637 1451 245 *************************************************************** 3637 1451 246 1. Theoretical models 3637 1451 247 The POD code is based on the spherical optical model, the 3637 1451 248 distorted-wave Born approximaiton (DWBA), one-component exciton 3637 1451 249 preequilibrium model, and the Hauser-Feshbach-Moldauer statis- 3637 1451 250 tical model. With the preequilibrim model, semi-empirical 3637 1451 251 pickup and knockout process can be taken into account for 3637 1451 252 composite-particle emission. The gamma-ray emission from the 3637 1451 253 compound nucleus can be calculated within the framework of the 3637 1451 254 exciton model. The code is capable of reading in particle 3637 1451 255 transmission coefficients calculated by separate spherical or 3637 1451 256 coupled-channel optical model code. 3637 1451 257 3637 1451 258 2. Optical model parameters 3637 1451 259 Neutrons: 3637 1451 260 Coupled-channel optical model parameters /4/ 3637 1451 261 Protons: 3637 1451 262 Koning and Delaroche /5/ 3637 1451 263 Deuterons: 3637 1451 264 Lohr and Haeberli /6/ 3637 1451 265 Tritons: 3637 1451 266 Becchetti and Greenlees /7/ 3637 1451 267 He-3: 3637 1451 268 Becchetti and Greenlees /7/ 3637 1451 269 Alphas: 3637 1451 270 Lemos /8/ potentials modified by Arthur and Young /9/ 3637 1451 271 3637 1451 272 3. Level scheme of Kr- 82 3637 1451 273 ------------------------- 3637 1451 274 No. Ex(MeV) J PI 3637 1451 275 ------------------------- 3637 1451 276 0 0.00000 0 + 3637 1451 277 1 0.77652 2 + 3637 1451 278 2 1.47490 2 + 3637 1451 279 3 1.48762 0 + 3637 1451 280 4 1.82053 4 + 3637 1451 281 5 1.88500 2 - 3637 1451 282 6 1.95679 2 + 3637 1451 283 7 2.09401 3 + 3637 1451 284 8 2.17168 0 + 3637 1451 285 9 2.42688 4 + 3637 1451 286 10 2.45009 2 + 3637 1451 287 11 2.47972 2 + 3637 1451 288 12 2.54775 3 - 3637 1451 289 13 2.55618 4 + 3637 1451 290 14 2.64836 4 - 3637 1451 291 15 2.65586 1 - 3637 1451 292 16 2.82810 5 - 3637 1451 293 17 2.84974 4 + 3637 1451 294 18 2.91971 6 + 3637 1451 295 19 2.94414 2 + 3637 1451 296 20 3.01106 5 - 3637 1451 297 21 3.03780 6 - 3637 1451 298 22 3.07700 5 + 3637 1451 299 23 3.16755 6 + 3637 1451 300 24 3.18682 1 + 3637 1451 301 25 3.18692 1 - 3637 1451 302 ------------------------- 3637 1451 303 Levels above 3.19692 MeV are assumed to be continuous. 3637 1451 304 3637 1451 305 4. Level density parameters 3637 1451 306 Energy-dependent parameters of Mengoni-Nakajima /10/ were used 3637 1451 307 ---------------------------------------------------------- 3637 1451 308 Nuclei a* Pair Esh T E0 Ematch Elv_max 3637 1451 309 1/MeV MeV MeV MeV MeV MeV MeV 3637 1451 310 ---------------------------------------------------------- 3637 1451 311 Kr- 83 11.668 1.317 2.381 0.710 -0.316 6.290 1.889 3637 1451 312 Kr- 82 10.867 2.650 2.503 0.781 0.700 8.353 3.187 3637 1451 313 Kr- 81 11.444 1.333 3.305 0.766 -1.104 7.552 1.829 3637 1451 314 Kr- 80 10.645 2.683 3.049 0.643 1.801 6.353 3.699 3637 1451 315 Br- 82 10.599 0.000 2.092 0.832 -2.117 6.154 1.261 3637 1451 316 Br- 81 10.293 1.333 2.879 0.880 -1.411 8.480 1.587 3637 1451 317 Br- 80 10.191 0.000 3.385 0.903 -3.155 7.747 0.771 3637 1451 318 Se- 80 10.645 2.683 2.442 0.815 0.539 8.768 3.226 3637 1451 319 Se- 79 10.473 1.350 3.245 0.875 -1.656 8.768 0.729 3637 1451 320 Se- 78 9.830 2.717 3.184 0.927 -0.352 10.456 3.090 3637 1451 321 ---------------------------------------------------------- 3637 1451 322 3637 1451 323 5. Gamma-ray strength functions 3637 1451 324 M1, E2: Standard Lorentzian (SLO) 3637 1451 325 E1 : Generalized Lorentzian (GLO) /11/ 3637 1451 326 3637 1451 327 6. Preequilibrium process 3637 1451 328 Preequilibrium is on for n, p, d, t, He-3, and alpha. 3637 1451 329 Preequilibrium capture is on. 3637 1451 330 3637 1451 331 References 3637 1451 332 1) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I, 3637 1451 333 Part A", Academic Press (1981). 3637 1451 334 2) Mughabghab, S.F.: "Atlas of Neutron Resonances", Elsevier 3637 1451 335 (2006). 3637 1451 336 3) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 3637 1451 337 4) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 3637 1451 338 5) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 3637 1451 339 6) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 3637 1451 340 7) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization 3637 1451 341 Phenomena in Nuclear Reactions," p.682, The University 3637 1451 342 of Wisconsin Press (1971). 3637 1451 343 8) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 3637 1451 344 9) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 3637 1451 345 10) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 3637 1451 346 (1994). 3637 1451 347 11) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990). 3637 1451 348 3637 1451 349 1 451 373 13637 1451 350 2 151 4 13637 1451 351 3 4 23 13637 1451 352 3 16 7 13637 1451 353 3 17 4 13637 1451 354 3 22 7 13637 1451 355 3 28 7 13637 1451 356 3 102 239 13637 1451 357 3 103 12 13637 1451 358 3 104 8 13637 1451 359 3 105 7 13637 1451 360 3 106 6 13637 1451 361 3 107 11 13637 1451 362 8 4 2 13637 1451 363 8 16 2 13637 1451 364 8 17 2 13637 1451 365 8 22 2 13637 1451 366 8 28 2 13637 1451 367 8 102 2 13637 1451 368 8 103 2 13637 1451 369 8 104 2 13637 1451 370 8 105 2 13637 1451 371 8 106 2 13637 1451 372 8 107 2 13637 1451 373 3637 1 099999 3637 0 0 0 3.608200+4 8.120981+1 0 0 1 03637 2151 1 3.608200+4 1.000000+0 0 0 1 03637 2151 2 1.000000-5 4.000000+2 0 0 0 03637 2151 3 0.000000+0 7.300000-1 0 0 0 03637 2151 4 3637 2 099999 3637 0 0 0 3.608200+4 8.120981+1 0 0 0 03637 3 4 1 0.000000+0-7.765210+5 0 0 1 583637 3 4 2 58 2 3637 3 4 3 7.860829+5 0.000000+0 8.000000+5 1.400000-1 9.000000+5 4.723000-13637 3 4 4 1.000000+6 6.920000-1 1.493062+6 1.089408+0 1.500000+6 1.136120+03637 3 4 5 1.505938+6 1.137693+0 1.842948+6 1.329237+0 1.908211+6 1.395594+03637 3 4 6 1.980885+6 1.537773+0 2.000000+6 1.609590+0 2.119795+6 1.623129+03637 3 4 7 2.198422+6 1.664421+0 2.456764+6 1.843739+0 2.480260+6 1.864996+03637 3 4 8 2.500000+6 1.899075+0 2.510255+6 1.893941+0 2.579122+6 1.876848+03637 3 4 9 2.587656+6 1.876289+0 2.680971+6 1.883524+0 2.688564+6 1.884983+03637 3 4 10 2.862925+6 1.955233+0 2.884831+6 1.964581+0 2.955663+6 2.003605+03637 3 4 11 2.980394+6 2.017347+0 3.000000+6 2.036322+0 3.048138+6 2.028925+03637 3 4 12 3.075207+6 2.025319+0 3.114890+6 2.020376+0 3.206555+6 2.013144+03637 3 4 13 3.226062+6 2.011686+0 3.226163+6 2.011692+0 3.236286+6 2.013577+03637 3 4 14 3.500000+6 2.143769+0 4.000000+6 2.097023+0 4.500000+6 2.043841+03637 3 4 15 5.000000+6 1.990271+0 5.500000+6 1.946764+0 6.000000+6 1.911831+03637 3 4 16 6.500000+6 1.886338+0 7.000000+6 1.867304+0 7.500000+6 1.853039+03637 3 4 17 8.000000+6 1.841688+0 8.500000+6 1.832104+0 9.000000+6 1.823156+03637 3 4 18 9.500000+6 1.814609+0 1.000000+7 1.805660+0 1.100000+7 1.788038+03637 3 4 19 1.200000+7 1.458121+0 1.300000+7 1.019404+0 1.400000+7 7.443624-13637 3 4 20 1.450000+7 6.594254-1 1.500000+7 5.850590-1 1.600000+7 4.893586-13637 3 4 21 1.700000+7 4.279162-1 1.800000+7 3.843138-1 1.900000+7 3.519897-13637 3 4 22 2.000000+7 3.263339-1 3637 3 4 23 3637 3 099999 3.608200+4 8.120981+1 0 0 0 03637 3 16 1 -1.096679+7-1.096679+7 0 0 1 113637 3 16 2 11 2 3637 3 16 3 1.110183+7 0.000000+0 1.200000+7 3.122000-1 1.300000+7 7.324000-13637 3 16 4 1.400000+7 9.856000-1 1.450000+7 1.051000+0 1.500000+7 1.118000+03637 3 16 5 1.600000+7 1.185000+0 1.700000+7 1.218000+0 1.800000+7 1.235000+03637 3 16 6 1.900000+7 1.245000+0 2.000000+7 1.250000+0 3637 3 16 7 3637 3 099999 3.608200+4 8.120981+1 0 0 0 03637 3 17 1 -1.883965+7-1.883965+7 0 0 1 23637 3 17 2 2 2 3637 3 17 3 1.907164+7 0.000000+0 2.000000+7 1.634000-3 3637 3 17 4 3637 3 099999 3.608200+4 8.120981+1 0 0 0 03637 3 22 1 -5.988337+6-5.988337+6 0 0 1 113637 3 22 2 11 2 3637 3 22 3 6.062076+6 0.000000+0 1.200000+7 0.000000+0 1.300000+7 2.412000-63637 3 22 4 1.400000+7 2.680000-5 1.450000+7 6.533000-5 1.500000+7 1.393000-43637 3 22 5 1.600000+7 4.519000-4 1.700000+7 1.072000-3 1.800000+7 1.978000-33637 3 22 6 1.900000+7 3.048000-3 2.000000+7 4.146000-3 3637 3 22 7 3637 3 099999 3.608200+4 8.120981+1 0 0 0 03637 3 28 1 -9.903640+6-9.903640+6 0 0 1 123637 3 28 2 12 2 3637 3 28 3 1.002559+7 0.000000+0 1.100000+7 0.000000+0 1.200000+7 1.047000-63637 3 28 4 1.300000+7 9.824000-5 1.400000+7 9.952000-4 1.450000+7 2.229000-33637 3 28 5 1.500000+7 3.927000-3 1.600000+7 8.713000-3 1.700000+7 1.436000-23637 3 28 6 1.800000+7 1.982000-2 1.900000+7 2.524000-2 2.000000+7 3.064000-23637 3 28 7 3637 3 099999 3.608200+4 8.120981+1 0 0 0 03637 3102 1 7.463518+6 7.463518+6 0 0 1 7073637 3102 2 707 2 3637 3102 3 1.000000-5 9.585603+2 1.103037-5 9.126924+2 1.216691-5 8.690192+23637 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