JENDL-5 (Neutron sublibrary (activation cs)) Y - 91 0 0 0 0 3.909100+4 9.012637+1 0 0 6 13931 1451 1 0.000000+0 1.000000+0 0 0 0 63931 1451 2 1.000000+0 2.000000+7 0 0 10 53931 1451 3 2.936000+2 0.000000+0 4 0 347 263931 1451 4 39-Y - 91 JAEA EVAL-NOV09 A.Ichihara, K.Shibata, S.Kunieda+3931 1451 5 DIST-DEC21 20100209 3931 1451 6 ----JENDL-5 MATERIAL 3931 3931 1451 7 -----INCIDENT NEUTRON DATA 3931 1451 8 ------ENDF-6 FORMAT 3931 1451 9 3931 1451 10 History 3931 1451 11 09-11 Compiled by A.Ichihara 3931 1451 12 21-11 revised by O.Iwamoto 3931 1451 13 (MF8/MT4,16,17,22,28,32,102-107) added 3931 1451 14 21-11 above 20 MeV, JENDL/ImPACT-2018 merged by O.Iwamoto 3931 1451 15 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 3931 1451 16 3931 1451 17 3931 1451 18 MF= 1 General information 3931 1451 19 MT=451 Descriptive data and directory 3931 1451 20 3931 1451 21 Cross sections were calculated with the POD code/1/ in 3931 1451 22 the neutron energy range from 300 eV to 20 MeV. 3931 1451 23 3931 1451 24 Cross sections below 300 eV were taken from JENDL-3.3. 3931 1451 25 In JENDL-3.3, the capture and elastic scattering cross sections 3931 1451 26 were assumed to be in 1/v form and constant, respectively. 3931 1451 27 The capture cross section at 0.0253 eV was adopted from /2/. 3931 1451 28 The scattering cross section was calculated from R = 6.7 fm. 3931 1451 29 3931 1451 30 MF= 2 Resonance parameters 3931 1451 31 MT=151 Unresolved resonance region : 300 eV - 200 keV 3931 1451 32 The unresolved resonance parameters were calculated using 3931 1451 33 the ASREP code/3/. 3931 1451 34 The parameters should be used only for self-shielding 3931 1451 35 calculation. 3931 1451 36 3931 1451 37 Thermal cross sections and resonance integrals at 300 K 3931 1451 38 ---------------------------------------------------------- 3931 1451 39 0.0253 eV res. integ. (*) 3931 1451 40 (barns) (barns) 3931 1451 41 ---------------------------------------------------------- 3931 1451 42 Total 7.1488E+00 3931 1451 43 Elastic 5.7323E+00 3931 1451 44 n,gamma 1.4005E+00 3.7661E+00 3931 1451 45 ---------------------------------------------------------- 3931 1451 46 (*) Integrated from 0.5 eV to 10 MeV. 3931 1451 47 3931 1451 48 MF= 3 Neutron cross sections 3931 1451 49 MT= 1 Total cross section 3931 1451 50 Calculated with POD code /1/. 3931 1451 51 3931 1451 52 MT= 2 Elastic scattering cross section 3931 1451 53 Calculated as (total - sum of partial cross sections). 3931 1451 54 3931 1451 55 MT= 3 Non-elastic cross section 3931 1451 56 Calculated as sum of partial cross sections. 3931 1451 57 3931 1451 58 MT= 4,51-91 (n,n') cross section 3931 1451 59 Calculated with POD code /1/. 3931 1451 60 3931 1451 61 MT= 16 (n,2n) cross section 3931 1451 62 Calculated with POD code /1/. 3931 1451 63 3931 1451 64 MT= 17 (n,3n) cross section 3931 1451 65 Calculated with POD code /1/. 3931 1451 66 3931 1451 67 MT= 22 (n,na) cross section 3931 1451 68 Calculated with POD code /1/. 3931 1451 69 3931 1451 70 MT= 28 (n,np) cross section 3931 1451 71 Calculated with POD code /1/. 3931 1451 72 3931 1451 73 MT= 32 (n,nd) cross section 3931 1451 74 Calculated with POD code /1/. 3931 1451 75 3931 1451 76 MT=102 Capture cross section 3931 1451 77 Calculated with POD code /1/. 3931 1451 78 3931 1451 79 MT=103 (n,p) cross section 3931 1451 80 Calculated with POD code /1/. 3931 1451 81 3931 1451 82 MT=104 (n,d) cross section 3931 1451 83 Calculated with POD code /1/. 3931 1451 84 3931 1451 85 MT=105 (n,t) cross section 3931 1451 86 Calculated with POD code /1/. 3931 1451 87 3931 1451 88 MT=106 (n,He3) cross section 3931 1451 89 Calculated with POD code /1/. 3931 1451 90 3931 1451 91 MT=107 (n,a) cross section 3931 1451 92 Calculated with POD code /1/. 3931 1451 93 3931 1451 94 MT=203 (n,xp) cross section 3931 1451 95 Calculated with POD code /1/. 3931 1451 96 3931 1451 97 MT=204 (n,xd) cross section 3931 1451 98 Calculated with POD code /1/. 3931 1451 99 3931 1451 100 MT=205 (n,xt) cross section 3931 1451 101 Calculated with POD code /1/. 3931 1451 102 3931 1451 103 MT=206 (n,xHe3) cross section 3931 1451 104 Calculated with POD code /1/. 3931 1451 105 3931 1451 106 MT=207 (n,xa) cross section 3931 1451 107 Calculated with POD code /1/. 3931 1451 108 3931 1451 109 MF= 4 Angular distributions of emitted neutrons 3931 1451 110 MT= 2 Elastic scattering 3931 1451 111 Calculated with POD code /1/. 3931 1451 112 3931 1451 113 MF= 6 Energy-angle distributions of emitted particles 3931 1451 114 MT= 16 (n,2n) reaction 3931 1451 115 Neutron spectra calculated with POD/1/. 3931 1451 116 3931 1451 117 MT= 17 (n,3n) reaction 3931 1451 118 Neutron spectra calculated with POD/1/. 3931 1451 119 3931 1451 120 MT= 22 (n,na) reaction 3931 1451 121 Neutron spectra calculated with POD/1/. 3931 1451 122 3931 1451 123 MT= 28 (n,np) reaction 3931 1451 124 Neutron spectra calculated with POD/1/. 3931 1451 125 3931 1451 126 MT= 32 (n,nd) reaction 3931 1451 127 Neutron spectra calculated with POD/1/. 3931 1451 128 3931 1451 129 MT= 51 (n,n') reaction 3931 1451 130 Neutron angular distributions calculated with POD/1/. 3931 1451 131 3931 1451 132 MT= 52 (n,n') reaction 3931 1451 133 Neutron angular distributions calculated with POD/1/. 3931 1451 134 3931 1451 135 MT= 53 (n,n') reaction 3931 1451 136 Neutron angular distributions calculated with POD/1/. 3931 1451 137 3931 1451 138 MT= 54 (n,n') reaction 3931 1451 139 Neutron angular distributions calculated with POD/1/. 3931 1451 140 3931 1451 141 MT= 55 (n,n') reaction 3931 1451 142 Neutron angular distributions calculated with POD/1/. 3931 1451 143 3931 1451 144 MT= 56 (n,n') reaction 3931 1451 145 Neutron angular distributions calculated with POD/1/. 3931 1451 146 3931 1451 147 MT= 57 (n,n') reaction 3931 1451 148 Neutron angular distributions calculated with POD/1/. 3931 1451 149 3931 1451 150 MT= 58 (n,n') reaction 3931 1451 151 Neutron angular distributions calculated with POD/1/. 3931 1451 152 3931 1451 153 MT= 59 (n,n') reaction 3931 1451 154 Neutron angular distributions calculated with POD/1/. 3931 1451 155 3931 1451 156 MT= 60 (n,n') reaction 3931 1451 157 Neutron angular distributions calculated with POD/1/. 3931 1451 158 3931 1451 159 MT= 61 (n,n') reaction 3931 1451 160 Neutron angular distributions calculated with POD/1/. 3931 1451 161 3931 1451 162 MT= 62 (n,n') reaction 3931 1451 163 Neutron angular distributions calculated with POD/1/. 3931 1451 164 3931 1451 165 MT= 63 (n,n') reaction 3931 1451 166 Neutron angular distributions calculated with POD/1/. 3931 1451 167 3931 1451 168 MT= 64 (n,n') reaction 3931 1451 169 Neutron angular distributions calculated with POD/1/. 3931 1451 170 3931 1451 171 MT= 65 (n,n') reaction 3931 1451 172 Neutron angular distributions calculated with POD/1/. 3931 1451 173 3931 1451 174 MT= 66 (n,n') reaction 3931 1451 175 Neutron angular distributions calculated with POD/1/. 3931 1451 176 3931 1451 177 MT= 67 (n,n') reaction 3931 1451 178 Neutron angular distributions calculated with POD/1/. 3931 1451 179 3931 1451 180 MT= 68 (n,n') reaction 3931 1451 181 Neutron angular distributions calculated with POD/1/. 3931 1451 182 3931 1451 183 MT= 69 (n,n') reaction 3931 1451 184 Neutron angular distributions calculated with POD/1/. 3931 1451 185 3931 1451 186 MT= 70 (n,n') reaction 3931 1451 187 Neutron angular distributions calculated with POD/1/. 3931 1451 188 3931 1451 189 MT= 71 (n,n') reaction 3931 1451 190 Neutron angular distributions calculated with POD/1/. 3931 1451 191 3931 1451 192 MT= 72 (n,n') reaction 3931 1451 193 Neutron angular distributions calculated with POD/1/. 3931 1451 194 3931 1451 195 MT= 91 (n,n') reaction 3931 1451 196 Neutron spectra calculated with POD/1/. 3931 1451 197 3931 1451 198 MT= 203 (n,xp) reaction 3931 1451 199 Proton spectra calculated with POD/1/. 3931 1451 200 3931 1451 201 MT= 204 (n,xd) reaction 3931 1451 202 Deuteron spectra calculated with POD/1/. 3931 1451 203 3931 1451 204 MT= 205 (n,xt) reaction 3931 1451 205 Triton spectra calculated with POD/1/. 3931 1451 206 3931 1451 207 MT= 206 (n,xHe3) reaction 3931 1451 208 He3 spectra calculated with POD/1/. 3931 1451 209 3931 1451 210 MT= 207 (n,xa) reaction 3931 1451 211 Alpha spectra calculated with POD/1/. 3931 1451 212 3931 1451 213 MF=12 Gamma-ray multiplicities 3931 1451 214 MT= 3 Non-elastic gamma emission 3931 1451 215 Calculated with POD code /1/. 3931 1451 216 3931 1451 217 MF=14 Gamma-ray angular distributions 3931 1451 218 MT= 3 Non-elastic gamma emission 3931 1451 219 Assumed to be isotropic. 3931 1451 220 3931 1451 221 MF=15 Gamma-ray spectra 3931 1451 222 MT= 3 Non-elastic gamma emission 3931 1451 223 Calculated with POD code /1/. 3931 1451 224 3931 1451 225 3931 1451 226 3931 1451 227 *************************************************************** 3931 1451 228 * Nuclear Model Calculations with POD Code /1/ * 3931 1451 229 *************************************************************** 3931 1451 230 1. Theoretical models 3931 1451 231 The POD code is based on the spherical optical model, the 3931 1451 232 distorted-wave Born approximation (DWBA), one-component exciton 3931 1451 233 preequilibrium model, and the Hauser-Feshbach-Moldauer statis- 3931 1451 234 tical model. With the preequilibrim model, semi-empirical 3931 1451 235 pickup and knockout process can be taken into account for 3931 1451 236 composite-particle emission. The gamma-ray emission from the 3931 1451 237 compound nucleus can be calculated within the framework of the 3931 1451 238 exciton model. The code is capable of reading in particle 3931 1451 239 transmission coefficients calculated by separate spherical or 3931 1451 240 coupled-channel optical model code. 3931 1451 241 3931 1451 242 2. Optical model parameters 3931 1451 243 Neutrons: 3931 1451 244 Koning and Delaroche /4/ 3931 1451 245 Protons: 3931 1451 246 Koning and Delaroche /4/ 3931 1451 247 The radius parameter r_V = 1.25 fm was used in the calculation. 3931 1451 248 Deuterons: 3931 1451 249 Lohr and Haeberli /5/ 3931 1451 250 Tritons: 3931 1451 251 Becchetti and Greenlees /6/ 3931 1451 252 He-3: 3931 1451 253 Becchetti and Greenlees /6/ 3931 1451 254 Alphas: 3931 1451 255 Lemos /7/ potentials modified by Arthur and Young /8/. 3931 1451 256 The radius parameters r_V = r_I = 1.40 fm were used in the 3931 1451 257 calculation. 3931 1451 258 3931 1451 259 3. Level scheme of Y - 91 3931 1451 260 Nuclear discrete levels were obtained from RIPL-2/9/. 3931 1451 261 ------------------------- 3931 1451 262 No. Ex(MeV) J PI 3931 1451 263 ------------------------- 3931 1451 264 0 0.00000 1/2 - 3931 1451 265 1 0.55558 9/2 + 3931 1451 266 2 0.65303 3/2 - 3931 1451 267 3 0.92575 5/2 - 3931 1451 268 4 1.18689 7/2 - 3931 1451 269 5 1.30540 5/2 + 3931 1451 270 6 1.47370 3/2 - 3931 1451 271 7 1.54591 5/2 - 3931 1451 272 8 1.54800 7/2 - 3931 1451 273 9 1.57994 7/2 + 3931 1451 274 10 1.98042 3/2 - 3931 1451 275 11 2.06663 5/2 + 3931 1451 276 12 2.12910 3/2 + 3931 1451 277 13 2.16300 3/2 - 3931 1451 278 14 2.20676 5/2 - 3931 1451 279 15 2.27935 7/2 - 3931 1451 280 16 2.41220 3/2 - 3931 1451 281 17 2.47400 3/2 - 3931 1451 282 18 2.53000 5/2 - 3931 1451 283 19 2.57000 1/2 - 3931 1451 284 20 2.57214 7/2 - 3931 1451 285 21 2.63100 5/2 - 3931 1451 286 22 2.68900 7/2 - 3931 1451 287 ------------------------- 3931 1451 288 Levels above 2.69900 MeV are assumed to be continuous. 3931 1451 289 3931 1451 290 4. Level density parameters 3931 1451 291 Energy-dependent parameters of Mengoni-Nakajima /10/ were used 3931 1451 292 --------------------------------------------------- 3931 1451 293 Nuclei a* Pair T E0 Ematch Elv_max 3931 1451 294 1/MeV MeV MeV MeV MeV MeV 3931 1451 295 --------------------------------------------------- 3931 1451 296 Y - 92 11.929 0.000 0.493 0.199 1.501 2.900 3931 1451 297 Y - 91 11.338 1.258 0.772 0.115 5.977 2.689 3931 1451 298 Y - 90 10.454 0.000 0.865 -0.779 4.677 2.624 3931 1451 299 Y - 89 11.127 1.272 0.682 1.455 3.665 4.023 3931 1451 300 Sr- 91 12.543 1.258 0.625 0.591 4.649 4.249 3931 1451 301 Sr- 90 11.748 2.530 0.778 1.141 7.584 3.627 3931 1451 302 Sr- 89 10.953 1.272 0.720 1.044 4.474 4.050 3931 1451 303 Rb- 89 11.127 1.272 0.818 -0.434 6.915 1.999 3931 1451 304 Rb- 88 10.411 0.000 0.994 -2.333 7.292 1.964 3931 1451 305 Rb- 87 10.916 1.287 0.895 -0.274 7.103 3.099 3931 1451 306 --------------------------------------------------- 3931 1451 307 3931 1451 308 5. Gamma-ray strength functions 3931 1451 309 M1, E2: Standard Lorentzian (SLO) 3931 1451 310 E1 : Standard Lorentzian (SLO) /11/ 3931 1451 311 The position and width parameters in the E1 3931 1451 312 radiation were taken from the tabulation of 3931 1451 313 Dietrich and Berman/12/. 3931 1451 314 3931 1451 315 6. Preequilibrium process 3931 1451 316 Preequilibrium is on for n, p, d, t, He-3, and alpha. 3931 1451 317 3931 1451 318 The single particle state density parameters were 3931 1451 319 7.390, 6.958, 7.877, 6.188, 7.202, 5.500, 7.059 (MeV^-1) 3931 1451 320 for Y-92, Y-91, Sr-91, Rb-88, Sr-90, Sr-89, and Rb-89. 3931 1451 321 3931 1451 322 Effects of the particle pickup (and knockout for alpha) were 3931 1451 323 estimated using the semi-empirical formulas by Kalbach/13/. 3931 1451 324 These components were multiplied by a factor of two and 3931 1451 325 added to the statistical model calculation. 3931 1451 326 3931 1451 327 Preequilibrium capture is on (the parameters were obtained 3931 1451 328 from /12/). 3931 1451 329 3931 1451 330 References 3931 1451 331 1) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 3931 1451 332 2) S.F.Mughabghab et al., "Neutron Cross Sections, Vol. I, 3931 1451 333 Part A," Academic Press (1981). 3931 1451 334 3) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999) 3931 1451 335 [in Japanese]. 3931 1451 336 4) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 3931 1451 337 5) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 3931 1451 338 6) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization 3931 1451 339 Phenomena in Nuclear Reactions," p.682, The University 3931 1451 340 of Wisconsin Press (1971). 3931 1451 341 7) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 3931 1451 342 8) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 3931 1451 343 9) T.Belgya et al., IAEA-TECDOC-1506 (2006). 3931 1451 344 10) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 3931 1451 345 (1994). 3931 1451 346 11) M.Brink, Ph.D thesis, Oxford University, 1955. 3931 1451 347 12) S.S.Dietrich, B.L.Berman, Atom. Data Nucl. Data Tables, 3931 1451 348 38, 199 (1988). 3931 1451 349 13) C.Kalbach, Z. Phys. A283, 401 (1977). 3931 1451 350 3931 1451 351 1 451 377 13931 1451 352 2 151 4 13931 1451 353 3 4 24 13931 1451 354 3 16 8 13931 1451 355 3 17 6 13931 1451 356 3 22 7 13931 1451 357 3 28 8 13931 1451 358 3 32 6 13931 1451 359 3 102 131 13931 1451 360 3 103 10 13931 1451 361 3 104 8 13931 1451 362 3 105 8 13931 1451 363 3 106 5 13931 1451 364 3 107 11 13931 1451 365 8 4 2 13931 1451 366 8 16 2 13931 1451 367 8 17 2 13931 1451 368 8 22 2 13931 1451 369 8 28 2 13931 1451 370 8 32 2 13931 1451 371 8 102 2 13931 1451 372 8 103 2 13931 1451 373 8 104 2 13931 1451 374 8 105 2 13931 1451 375 8 106 2 13931 1451 376 8 107 2 13931 1451 377 3931 1 099999 3931 0 0 0 3.909100+4 9.012637+1 0 0 1 03931 2151 1 3.909100+4 1.000000+0 0 0 1 03931 2151 2 3.000000+2 2.000000+5 0 0 0 03931 2151 3 5.000000-1 6.484600-1 0 0 0 03931 2151 4 3931 2 099999 3931 0 0 0 3.909100+4 9.012637+1 0 0 0 03931 3 4 1 0.000000+0-5.555800+5 0 0 1 623931 3 4 2 62 2 3931 3 4 3 5.617445+5 0.000000+0 6.000000+5 2.841000-2 6.602757+5 4.509431-23931 3 4 4 7.000000+5 2.424900-1 8.000000+5 6.087600-1 9.000000+5 8.096500-13931 3 4 5 9.360217+5 8.267783-1 1.000000+6 9.949000-1 1.200000+6 1.229700+03931 3 4 6 1.200059+6 1.229683+0 1.319884+6 1.289803+0 1.400000+6 1.402040+03931 3 4 7 1.490051+6 1.413053+0 1.563063+6 1.488215+0 1.565176+6 1.491863+03931 3 4 8 1.597470+6 1.561569+0 1.600000+6 1.570912+0 1.700000+6 1.672600+03931 3 4 9 1.800000+6 1.743200+0 1.900000+6 1.791310+0 2.000000+6 1.825200+03931 3 4 10 2.002394+6 1.824858+0 2.089560+6 1.853080+0 2.100000+6 1.861316+03931 3 4 11 2.152723+6 1.869527+0 2.187000+6 1.886770+0 2.200000+6 1.898690+03931 3 4 12 2.231245+6 1.903817+0 2.300000+6 1.939170+0 2.304641+6 1.939499+03931 3 4 13 2.400000+6 1.971590+0 2.438965+6 1.974111+0 2.500000+6 1.994260+03931 3 4 14 2.501450+6 1.993993+0 2.558072+6 1.997674+0 2.598516+6 2.010056+03931 3 4 15 2.600000+6 2.012704+0 2.600679+6 2.012443+0 2.660192+6 1.998384+03931 3 4 16 2.718836+6 1.995223+0 2.728947+6 1.996285+0 3.000000+6 2.112654+03931 3 4 17 3.500000+6 2.047656+0 4.000000+6 1.973263+0 4.500000+6 1.913930+03931 3 4 18 5.000000+6 1.874194+0 5.500000+6 1.853918+0 6.000000+6 1.846813+03931 3 4 19 7.000000+6 1.846329+0 8.000000+6 1.839771+0 9.000000+6 1.371938+03931 3 4 20 1.000000+7 8.559428-1 1.100000+7 5.503750-1 1.200000+7 3.850127-13931 3 4 21 1.330000+7 2.810884-1 1.400000+7 2.497511-1 1.500000+7 2.189900-13931 3 4 22 1.600000+7 1.987689-1 1.700000+7 1.808232-1 1.800000+7 1.658542-13931 3 4 23 1.900000+7 1.525781-1 2.000000+7 1.406939-1 3931 3 4 24 3931 3 099999 3.909100+4 9.012637+1 0 0 0 03931 3 16 1 -7.928887+6-7.928887+6 0 0 1 133931 3 16 2 13 2 3931 3 16 3 8.016862+6 0.000000+0 9.000000+6 4.526000-1 1.000000+7 9.505000-13931 3 16 4 1.100000+7 1.236000+0 1.200000+7 1.378000+0 1.330000+7 1.450000+03931 3 16 5 1.400000+7 1.464000+0 1.500000+7 1.470000+0 1.600000+7 1.456000+03931 3 16 6 1.700000+7 1.374000+0 1.800000+7 1.213000+0 1.900000+7 1.032000+03931 3 16 7 2.000000+7 8.571000-1 3931 3 16 8 3931 3 099999 3.909100+4 9.012637+1 0 0 0 03931 3 17 1 -1.478592+7-1.478592+7 0 0 1 73931 3 17 2 7 2 3931 3 17 3 1.494997+7 0.000000+0 1.500000+7 0.000000+0 1.600000+7 1.116000-23931 3 17 4 1.700000+7 8.832000-2 1.800000+7 2.435000-1 1.900000+7 4.166000-13931 3 17 5 2.000000+7 5.793000-1 3931 3 17 6 3931 3 099999 3.909100+4 9.012637+1 0 0 0 03931 3 22 1 -4.172152+6-4.172152+6 0 0 1 123931 3 22 2 12 2 3931 3 22 3 4.218444+6 0.000000+0 1.000000+7 0.000000+0 1.100000+7 1.139000-63931 3 22 4 1.200000+7 1.328000-5 1.330000+7 1.157000-4 1.400000+7 2.829000-43931 3 22 5 1.500000+7 7.591000-4 1.600000+7 1.538000-3 1.700000+7 2.520000-33931 3 22 6 1.800000+7 3.590000-3 1.900000+7 4.699000-3 2.000000+7 5.812000-33931 3 22 7 3931 3 099999 3.909100+4 9.012637+1 0 0 0 03931 3 28 1 -7.692398+6-7.692398+6 0 0 1 133931 3 28 2 13 2 3931 3 28 3 7.777749+6 0.000000+0 9.000000+6 0.000000+0 1.000000+7 2.122000-73931 3 28 4 1.100000+7 2.352000-5 1.200000+7 2.723000-4 1.330000+7 1.975000-33931 3 28 5 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