JENDL-5 (Neutron sublibrary (activation cs)) Kr- 83 0 0 0 0 3.608300+4 8.220186+1 0 0 6 13640 1451 1 0.000000+0 0.000000+0 0 0 0 63640 1451 2 1.000000+0 2.000000+7 0 0 10 53640 1451 3 2.936000+2 0.000000+0 4 0 347 263640 1451 4 36-Kr- 83 JAEA EVAL-AUG09 K.Shibata, A.Ichihara, S.Kunieda 3640 1451 5 DIST-DEC21 20091118 3640 1451 6 ----JENDL-5 MATERIAL 3640 3640 1451 7 -----INCIDENT NEUTRON DATA 3640 1451 8 ------ENDF-6 FORMAT 3640 1451 9 3640 1451 10 History 3640 1451 11 09-08 Evaluated by K. Shibata, A. Ichihara and S. Kunieda. 3640 1451 12 09-10 Compiled by K. Shibata. 3640 1451 13 21-11 revised by O.Iwamoto 3640 1451 14 (MF8/MT4,16,17,22,28,32,102-107) added 3640 1451 15 21-11 above 20 MeV, JENDL/ImPACT-2018 merged by O.Iwamoto 3640 1451 16 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 3640 1451 17 3640 1451 18 3640 1451 19 MF= 1 General information 3640 1451 20 MT=451 Descriptive data and directory 3640 1451 21 3640 1451 22 MF= 2 Resonance parameters 3640 1451 23 MT=151 Resolved and unresolved resonance parameters 3640 1451 24 Resolved resonance region (MLBW formula) : below 0.272 keV 3640 1451 25 For JENDL-2, parameters were given for 2 positive and a 3640 1451 26 negative resonances on the basis of the data given by 3640 1451 27 Mughabghab et al./1/ Neutron orbital angular momentum L 3640 1451 28 were assumed to be 0. Neutron widths were modified so as to3640 1451 29 reproduce the thermal capture cross section of 180+-30 barns3640 1451 30 and the neutron resonance capture integral of 183+-25 barns 3640 1451 31 given by Mughabghab et al. Radiation width of 210 meV for 3640 1451 32 the first level/1/ was adopted for the other resonance 3640 1451 33 levels. However, the values of total spin j were unknown 3640 1451 34 and the target spin of 4.5 was adopted for all the levels. 3640 1451 35 For JENDL-3, the J-values of all resonance levels were 3640 1451 36 tentatively estimated with a random number method. 3640 1451 37 According to modification of the J-values, resonance 3640 1451 38 parameters were also modified so as to reproduce the thermal3640 1451 39 capture cross section and the neutron resonance capture 3640 1451 40 integral mentioned above. Scattering radius was taken from 3640 1451 41 the graph (fig. 1, Part A) given by Mughabghab et al. 3640 1451 42 In JENDL-4, the radiation width of the negative resonance 3640 1451 43 was changed to 237 meV. 3640 1451 44 3640 1451 45 Unresolved resonance region: 272 eV - 260 keV 3640 1451 46 The parameters were obtained by fitting to the total and 3640 1451 47 capture cross sections calculated from POD /2/. The 3640 1451 48 unresolved parameters should be used only for self-shielding3640 1451 49 calculation. 3640 1451 50 3640 1451 51 Thermal cross sections and resonance integrals at 300 K 3640 1451 52 ---------------------------------------------------------- 3640 1451 53 0.0253 eV res. integ. (*) 3640 1451 54 (barns) (barns) 3640 1451 55 ---------------------------------------------------------- 3640 1451 56 Total 2.1147E+02 3640 1451 57 Elastic 9.1343E+00 3640 1451 58 n,gamma 2.0233E+02 1.5393E+02 3640 1451 59 ---------------------------------------------------------- 3640 1451 60 (*) Integrated from 0.5 eV to 10 MeV. 3640 1451 61 3640 1451 62 MF= 3 Neutron cross sections 3640 1451 63 MT= 1 Total cross section 3640 1451 64 Calculated with POD code /2/. 3640 1451 65 3640 1451 66 MT= 2 Elastic scattering cross section 3640 1451 67 Obtained by subtracting non-elastic cross secitons from total 3640 1451 68 cross sections. 3640 1451 69 3640 1451 70 MT= 3 Non-elastic cross section 3640 1451 71 Sum of partial non-elastic cross sections. 3640 1451 72 3640 1451 73 MT= 4,51-91 (n,n') cross section 3640 1451 74 Calculated with POD code /2/. 3640 1451 75 3640 1451 76 MT= 16 (n,2n) cross section 3640 1451 77 Calculated with POD code /2/. 3640 1451 78 3640 1451 79 MT= 17 (n,3n) cross section 3640 1451 80 Calculated with POD code /2/. 3640 1451 81 3640 1451 82 MT= 22 (n,na) cross section 3640 1451 83 Calculated with POD code /2/. 3640 1451 84 3640 1451 85 MT= 28 (n,np) cross section 3640 1451 86 Calculated with POD code /2/. 3640 1451 87 3640 1451 88 MT= 32 (n,nd) cross section 3640 1451 89 Calculated with POD code /2/. 3640 1451 90 3640 1451 91 MT=102 Capture cross section 3640 1451 92 Calculated with POD code /2/. 3640 1451 93 3640 1451 94 MT=103 (n,p) cross section 3640 1451 95 Calculated with POD code /2/. 3640 1451 96 3640 1451 97 MT=104 (n,d) cross section 3640 1451 98 Calculated with POD code /2/. 3640 1451 99 3640 1451 100 MT=105 (n,t) cross section 3640 1451 101 Calculated with POD code /2/. 3640 1451 102 3640 1451 103 MT=106 (n,He3) cross section 3640 1451 104 Calculated with POD code /2/. 3640 1451 105 3640 1451 106 MT=107 (n,a) cross section 3640 1451 107 Calculated with POD code /2/. 3640 1451 108 3640 1451 109 MT=203 (n,xp) cross section 3640 1451 110 Calculated with POD code /2/. 3640 1451 111 3640 1451 112 MT=204 (n,xd) cross section 3640 1451 113 Calculated with POD code /2/. 3640 1451 114 3640 1451 115 MT=205 (n,xt) cross section 3640 1451 116 Calculated with POD code /2/. 3640 1451 117 3640 1451 118 MT=206 (n,xHe3) cross section 3640 1451 119 Calculated with POD code /2/. 3640 1451 120 3640 1451 121 MT=207 (n,xa) cross section 3640 1451 122 Calculated with POD code /2/. 3640 1451 123 3640 1451 124 MF= 4 Angular distributions of emitted neutrons 3640 1451 125 MT= 2 Elastic scattering 3640 1451 126 Calculated with POD code /2/. 3640 1451 127 3640 1451 128 MF= 6 Energy-angle distributions of emitted particles 3640 1451 129 MT= 16 (n,2n) reaction 3640 1451 130 Neutron spectra calculated with POD/2/. 3640 1451 131 3640 1451 132 MT= 17 (n,3n) reaction 3640 1451 133 Neutron spectra calculated with POD/2/. 3640 1451 134 3640 1451 135 MT= 22 (n,na) reaction 3640 1451 136 Neutron spectra calculated with POD/2/. 3640 1451 137 3640 1451 138 MT= 28 (n,np) reaction 3640 1451 139 Neutron spectra calculated with POD/2/. 3640 1451 140 3640 1451 141 MT= 32 (n,nd) reaction 3640 1451 142 Neutron spectra calculated with POD/2/. 3640 1451 143 3640 1451 144 MT= 51 (n,n') reaction 3640 1451 145 Neutron angular distributions calculated with POD/2/. 3640 1451 146 3640 1451 147 MT= 52 (n,n') reaction 3640 1451 148 Neutron angular distributions calculated with POD/2/. 3640 1451 149 3640 1451 150 MT= 53 (n,n') reaction 3640 1451 151 Neutron angular distributions calculated with POD/2/. 3640 1451 152 3640 1451 153 MT= 54 (n,n') reaction 3640 1451 154 Neutron angular distributions calculated with POD/2/. 3640 1451 155 3640 1451 156 MT= 55 (n,n') reaction 3640 1451 157 Neutron angular distributions calculated with POD/2/. 3640 1451 158 3640 1451 159 MT= 56 (n,n') reaction 3640 1451 160 Neutron angular distributions calculated with POD/2/. 3640 1451 161 3640 1451 162 MT= 57 (n,n') reaction 3640 1451 163 Neutron angular distributions calculated with POD/2/. 3640 1451 164 3640 1451 165 MT= 58 (n,n') reaction 3640 1451 166 Neutron angular distributions calculated with POD/2/. 3640 1451 167 3640 1451 168 MT= 59 (n,n') reaction 3640 1451 169 Neutron angular distributions calculated with POD/2/. 3640 1451 170 3640 1451 171 MT= 60 (n,n') reaction 3640 1451 172 Neutron angular distributions calculated with POD/2/. 3640 1451 173 3640 1451 174 MT= 61 (n,n') reaction 3640 1451 175 Neutron angular distributions calculated with POD/2/. 3640 1451 176 3640 1451 177 MT= 62 (n,n') reaction 3640 1451 178 Neutron angular distributions calculated with POD/2/. 3640 1451 179 3640 1451 180 MT= 63 (n,n') reaction 3640 1451 181 Neutron angular distributions calculated with POD/2/. 3640 1451 182 3640 1451 183 MT= 64 (n,n') reaction 3640 1451 184 Neutron angular distributions calculated with POD/2/. 3640 1451 185 3640 1451 186 MT= 65 (n,n') reaction 3640 1451 187 Neutron angular distributions calculated with POD/2/. 3640 1451 188 3640 1451 189 MT= 66 (n,n') reaction 3640 1451 190 Neutron angular distributions calculated with POD/2/. 3640 1451 191 3640 1451 192 MT= 67 (n,n') reaction 3640 1451 193 Neutron angular distributions calculated with POD/2/. 3640 1451 194 3640 1451 195 MT= 68 (n,n') reaction 3640 1451 196 Neutron angular distributions calculated with POD/2/. 3640 1451 197 3640 1451 198 MT= 69 (n,n') reaction 3640 1451 199 Neutron angular distributions calculated with POD/2/. 3640 1451 200 3640 1451 201 MT= 70 (n,n') reaction 3640 1451 202 Neutron angular distributions calculated with POD/2/. 3640 1451 203 3640 1451 204 MT= 71 (n,n') reaction 3640 1451 205 Neutron angular distributions calculated with POD/2/. 3640 1451 206 3640 1451 207 MT= 72 (n,n') reaction 3640 1451 208 Neutron angular distributions calculated with POD/2/. 3640 1451 209 3640 1451 210 MT= 73 (n,n') reaction 3640 1451 211 Neutron angular distributions calculated with POD/2/. 3640 1451 212 3640 1451 213 MT= 74 (n,n') reaction 3640 1451 214 Neutron angular distributions calculated with POD/2/. 3640 1451 215 3640 1451 216 MT= 91 (n,n') reaction 3640 1451 217 Neutron spectra calculated with POD/2/. 3640 1451 218 3640 1451 219 MT= 203 (n,xp) reaction 3640 1451 220 Proton spectra calculated with POD/2/. 3640 1451 221 3640 1451 222 MT= 204 (n,xd) reaction 3640 1451 223 Deuteron spectra calculated with POD/2/. 3640 1451 224 3640 1451 225 MT= 205 (n,xt) reaction 3640 1451 226 Triton spectra calculated with POD/2/. 3640 1451 227 3640 1451 228 MT= 206 (n,xHe3) reaction 3640 1451 229 He3 spectra calculated with POD/2/. 3640 1451 230 3640 1451 231 MT= 207 (n,xa) reaction 3640 1451 232 Alpha spectra calculated with POD/2/. 3640 1451 233 3640 1451 234 MF=12 Gamma-ray multiplicities 3640 1451 235 MT= 3 Non-elastic gamma emission 3640 1451 236 Calculated with POD code /2/. 3640 1451 237 3640 1451 238 MF=14 Gamma-ray angular distributions 3640 1451 239 MT= 3 Non-elastic gamma emission 3640 1451 240 Assumed to be isotropic. 3640 1451 241 3640 1451 242 MF=15 Gamma-ray spectra 3640 1451 243 MT= 3 Non-elastic gamma emission 3640 1451 244 Calculated with POD code /2/. 3640 1451 245 3640 1451 246 3640 1451 247 3640 1451 248 *************************************************************** 3640 1451 249 * Nuclear Model Calculations with POD Code /2/ * 3640 1451 250 *************************************************************** 3640 1451 251 1. Theoretical models 3640 1451 252 The POD code is based on the spherical optical model, the 3640 1451 253 distorted-wave Born approximaiton (DWBA), one-component exciton 3640 1451 254 preequilibrium model, and the Hauser-Feshbach-Moldauer statis- 3640 1451 255 tical model. With the preequilibrim model, semi-empirical 3640 1451 256 pickup and knockout process can be taken into account for 3640 1451 257 composite-particle emission. The gamma-ray emission from the 3640 1451 258 compound nucleus can be calculated within the framework of the 3640 1451 259 exciton model. The code is capable of reading in particle 3640 1451 260 transmission coefficients calculated by separate spherical or 3640 1451 261 coupled-channel optical model code. 3640 1451 262 3640 1451 263 2. Optical model parameters 3640 1451 264 Neutrons: 3640 1451 265 Coupled-channel optical model parameters /3/ 3640 1451 266 Protons: 3640 1451 267 Koning and Delaroche /4/ 3640 1451 268 Deuterons: 3640 1451 269 Lohr and Haeberli /5/ 3640 1451 270 Tritons: 3640 1451 271 Becchetti and Greenlees /6/ 3640 1451 272 He-3: 3640 1451 273 Becchetti and Greenlees /6/ 3640 1451 274 Alphas: 3640 1451 275 Lemos /7/ potentials modified by Arthur and Young /8/ 3640 1451 276 3640 1451 277 3. Level scheme of Kr- 83 3640 1451 278 ------------------------- 3640 1451 279 No. Ex(MeV) J PI 3640 1451 280 ------------------------- 3640 1451 281 0 0.00000 9/2 + 3640 1451 282 1 0.00940 7/2 + 3640 1451 283 2 0.04154 1/2 - 3640 1451 284 3 0.56202 5/2 - 3640 1451 285 4 0.57120 3/2 - 3640 1451 286 5 0.69015 5/2 - 3640 1451 287 6 0.79890 5/2 + 3640 1451 288 7 0.81100 3/2 - 3640 1451 289 8 1.01186 11/2 + 3640 1451 290 9 1.10000 1/2 - 3640 1451 291 10 1.10289 9/2 + 3640 1451 292 11 1.12203 13/2 + 3640 1451 293 12 1.17040 7/2 - 3640 1451 294 13 1.22188 5/2 + 3640 1451 295 14 1.27790 1/2 + 3640 1451 296 15 1.51680 7/2 + 3640 1451 297 16 1.52916 9/2 - 3640 1451 298 17 1.53369 9/2 + 3640 1451 299 18 1.53810 7/2 - 3640 1451 300 19 1.64249 9/2 + 3640 1451 301 20 1.66800 7/2 - 3640 1451 302 21 1.72161 13/2 + 3640 1451 303 22 1.73847 11/2 + 3640 1451 304 23 1.78090 7/2 - 3640 1451 305 24 1.88890 7/2 - 3640 1451 306 ------------------------- 3640 1451 307 Levels above 1.89890 MeV are assumed to be continuous. 3640 1451 308 3640 1451 309 4. Level density parameters 3640 1451 310 Energy-dependent parameters of Mengoni-Nakajima /9/ were used 3640 1451 311 ---------------------------------------------------------- 3640 1451 312 Nuclei a* Pair Esh T E0 Ematch Elv_max 3640 1451 313 1/MeV MeV MeV MeV MeV MeV MeV 3640 1451 314 ---------------------------------------------------------- 3640 1451 315 Kr- 84 11.089 2.619 1.235 0.745 1.364 7.286 3.951 3640 1451 316 Kr- 83 11.668 1.317 2.381 0.710 -0.316 6.290 1.889 3640 1451 317 Kr- 82 10.867 2.650 2.503 0.781 0.700 8.353 3.187 3640 1451 318 Kr- 81 11.444 1.333 3.305 0.766 -1.104 7.552 1.829 3640 1451 319 Br- 83 10.507 1.317 1.382 0.813 -0.276 6.734 2.134 3640 1451 320 Br- 82 10.599 0.000 2.092 0.832 -2.117 6.154 1.261 3640 1451 321 Br- 81 10.293 1.333 2.879 0.880 -1.411 8.480 1.587 3640 1451 322 Se- 81 10.589 1.333 1.999 0.755 -0.063 6.204 2.253 3640 1451 323 Se- 80 10.645 2.683 2.442 0.815 0.539 8.768 3.226 3640 1451 324 Se- 79 10.473 1.350 3.245 0.875 -1.656 8.768 0.729 3640 1451 325 ---------------------------------------------------------- 3640 1451 326 3640 1451 327 5. Gamma-ray strength functions 3640 1451 328 M1, E2: Standard Lorentzian (SLO) 3640 1451 329 E1 : Generalized Lorentzian (GLO) /10/ 3640 1451 330 3640 1451 331 6. Preequilibrium process 3640 1451 332 Preequilibrium is on for n, p, d, t, He-3, and alpha. 3640 1451 333 Preequilibrium capture is on. 3640 1451 334 3640 1451 335 References 3640 1451 336 1) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I, 3640 1451 337 Part A", Academic Press (1981). 3640 1451 338 2) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 3640 1451 339 3) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 3640 1451 340 4) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 3640 1451 341 5) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 3640 1451 342 6) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization 3640 1451 343 Phenomena in Nuclear Reactions," p.682, The University 3640 1451 344 of Wisconsin Press (1971). 3640 1451 345 7) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 3640 1451 346 8) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 3640 1451 347 9) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 3640 1451 348 (1994). 3640 1451 349 10) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990). 3640 1451 350 3640 1451 351 1 451 377 13640 1451 352 2 151 4 13640 1451 353 3 4 28 13640 1451 354 3 16 9 13640 1451 355 3 17 4 13640 1451 356 3 22 7 13640 1451 357 3 28 7 13640 1451 358 3 32 5 13640 1451 359 3 102 346 13640 1451 360 3 103 13 13640 1451 361 3 104 8 13640 1451 362 3 105 7 13640 1451 363 3 106 6 13640 1451 364 3 107 13 13640 1451 365 8 4 2 13640 1451 366 8 16 2 13640 1451 367 8 17 2 13640 1451 368 8 22 2 13640 1451 369 8 28 2 13640 1451 370 8 32 2 13640 1451 371 8 102 2 13640 1451 372 8 103 2 13640 1451 373 8 104 2 13640 1451 374 8 105 2 13640 1451 375 8 106 2 13640 1451 376 8 107 2 13640 1451 377 3640 1 099999 3640 0 0 0 3.608300+4 8.220186+1 0 0 1 03640 2151 1 3.608300+4 1.000000+0 0 0 1 03640 2151 2 1.000000-5 2.720000+2 0 0 0 03640 2151 3 4.500000+0 7.030000-1 0 0 0 03640 2151 4 3640 2 099999 3640 0 0 0 3.608300+4 8.220186+1 0 0 0 03640 3 4 1 0.000000+0-9.396000+3 0 0 1 733640 3 4 2 73 2 3640 3 4 3 9.510304+3 0.000000+0 1.000000+4 5.489000-1 2.000000+4 5.010000-13640 3 4 4 3.000000+4 5.114000-1 4.000000+4 5.181000-1 4.204838+4 5.198206-13640 3 4 5 5.000000+4 5.265742-1 6.000000+4 5.373091-1 7.000000+4 5.491550-13640 3 4 6 8.000000+4 5.614044-1 9.000000+4 5.738662-1 1.000000+5 5.865398-13640 3 4 7 2.000000+5 6.955020-1 3.000000+5 7.562510-1 4.000000+5 7.803130-13640 3 4 8 5.000000+5 7.810100-1 5.688621+5 7.649720-1 5.781538+5 7.702920-13640 3 4 9 6.000000+5 7.845910-1 6.985458+5 7.908368-1 7.000000+5 7.970360-13640 3 4 10 8.000000+5 8.142400-1 8.086188+5 8.133454-1 8.208660+5 8.160251-13640 3 4 11 9.000000+5 8.368220-1 1.000000+6 8.574360-1 1.024169+6 8.469696-13640 3 4 12 1.113382+6 8.677509-1 1.116307+6 8.684513-1 1.135680+6 8.834559-13640 3 4 13 1.184638+6 9.494063-1 1.236744+6 1.034912+0 1.293446+6 1.136013+03640 3 4 14 1.500000+6 1.506247+0 1.535252+6 1.490035+0 1.547762+6 1.486094+03640 3 4 15 1.552348+6 1.485566+0 1.556811+6 1.486089+0 1.662471+6 1.510918+03640 3 4 16 1.688292+6 1.523219+0 1.742554+6 1.555813+0 1.759619+6 1.572301+03640 3 4 17 1.802565+6 1.627146+0 1.911879+6 1.780972+0 1.922000+6 1.796676+03640 3 4 18 2.000000+6 1.919758+0 2.500000+6 1.977816+0 3.000000+6 2.005889+03640 3 4 19 3.500000+6 2.016753+0 4.000000+6 1.994459+0 4.500000+6 1.947342+03640 3 4 20 5.000000+6 1.897346+0 5.500000+6 1.855207+0 6.000000+6 1.824192+03640 3 4 21 6.500000+6 1.802869+0 7.000000+6 1.788749+0 7.500000+6 1.778855+03640 3 4 22 8.000000+6 1.758882+0 8.500000+6 1.708148+0 9.000000+6 1.611271+03640 3 4 23 9.500000+6 1.487716+0 1.000000+7 1.355194+0 1.100000+7 1.072143+03640 3 4 24 1.200000+7 8.078392-1 1.300000+7 6.357779-1 1.400000+7 5.226562-13640 3 4 25 1.450000+7 4.708730-1 1.500000+7 4.361473-1 1.600000+7 3.725248-13640 3 4 26 1.700000+7 3.268869-1 1.800000+7 2.862136-1 1.900000+7 2.651852-13640 3 4 27 2.000000+7 2.450380-1 3640 3 4 28 3640 3 099999 3.608300+4 8.220186+1 0 0 0 03640 3 16 1 -7.463518+6-7.463518+6 0 0 1 173640 3 16 2 17 2 3640 3 16 3 7.554313+6 0.000000+0 8.000000+6 1.267000-2 8.500000+6 5.690000-23640 3 16 4 9.000000+6 1.476000-1 9.500000+6 2.655000-1 1.000000+7 3.902000-13640 3 16 5 1.100000+7 6.586000-1 1.200000+7 9.075000-1 1.300000+7 1.063000+03640 3 16 6 1.400000+7 1.155000+0 1.450000+7 1.196000+0 1.500000+7 1.218000+03640 3 16 7 1.600000+7 1.256000+0 1.700000+7 1.275000+0 1.800000+7 1.291000+03640 3 16 8 1.900000+7 1.290000+0 2.000000+7 1.268000+0 3640 3 16 9 3640 3 099999 3.608300+4 8.220186+1 0 0 0 03640 3 17 1 -1.843031+7-1.843031+7 0 0 1 33640 3 17 2 3 2 3640 3 17 3 1.865451+7 0.000000+0 1.900000+7 0.000000+0 2.000000+7 2.066000-23640 3 17 4 3640 3 099999 3.608300+4 8.220186+1 0 0 0 03640 3 22 1 -6.489023+6-6.489023+6 0 0 1 113640 3 22 2 11 2 3640 3 22 3 6.567963+6 0.000000+0 1.200000+7 0.000000+0 1.300000+7 3.179000-73640 3 22 4 1.400000+7 6.937000-6 1.450000+7 2.016000-5 1.500000+7 4.468000-53640 3 22 5 1.600000+7 1.666000-4 1.700000+7 4.392000-4 1.800000+7 8.661000-43640 3 22 6 1.900000+7 1.381000-3 2.000000+7 1.948000-3 3640 3 22 7 3640 3 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