JENDL-5 (Neutron sublibrary (activation cs)) Se- 79 0 0 0 0 3.407900+4 7.824055+1 0 0 6 13440 1451 1 0.000000+0 1.000000+0 0 0 0 63440 1451 2 1.000000+0 2.000000+7 0 0 10 53440 1451 3 2.936000+2 0.000000+0 4 0 286 263440 1451 4 34-Se- 79 JAEA EVAL-MAY09 S.Kamada, K.Shibata, A.Ichihara+ 3440 1451 5 DIST-DEC21 20091117 3440 1451 6 ----JENDL-5 MATERIAL 3440 3440 1451 7 -----INCIDENT NEUTRON DATA 3440 1451 8 ------ENDF-6 FORMAT 3440 1451 9 3440 1451 10 History 3440 1451 11 09-05 Evaluated by S. Kamada (TIT), K. Shibata (JAEA), A. Ichihara3440 1451 12 (JAEA) and S. Kunieda (JAEA) 3440 1451 13 09-10 Compiled by K. Shibata. 3440 1451 14 21-11 revised by O.Iwamoto 3440 1451 15 (MF8/MT4,16,17,22,28,32,102-107) added 3440 1451 16 21-11 above 20 MeV, JENDL/ImPACT-2018 merged by O.Iwamoto 3440 1451 17 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 3440 1451 18 3440 1451 19 3440 1451 20 MF= 1 General information 3440 1451 21 MT=451 Descriptive data and directory 3440 1451 22 3440 1451 23 MF= 2 Resonance parameters 3440 1451 24 MT=151 Resolved and unresolved resonance parameters 3440 1451 25 No resolved resonance region is given. 3440 1451 26 3440 1451 27 Unresolved resonance region: 38 eV - 500 keV 3440 1451 28 The parameters were obtained by fitting to the total and 3440 1451 29 capture cross sections calculated from POD /1/. The 3440 1451 30 unresolved parameters should be used only for self-shielding3440 1451 31 calculation. 3440 1451 32 3440 1451 33 Thermal cross sections and resonance integrals at 300 K 3440 1451 34 ---------------------------------------------------------- 3440 1451 35 0.0253 eV res. integ. (*) 3440 1451 36 (barns) (barns) 3440 1451 37 ---------------------------------------------------------- 3440 1451 38 Total 5.6464E+01 3440 1451 39 Elastic 6.3467E+00 3440 1451 40 n,gamma 5.0023E+01 1.0869E+02 3440 1451 41 ---------------------------------------------------------- 3440 1451 42 (*) Integrated from 0.5 eV to 10 MeV. 3440 1451 43 3440 1451 44 MF= 3 Neutron cross sections 3440 1451 45 MT= 1 Total cross section 3440 1451 46 Below 38 eV, the cross section is a sum of elastic and 3440 1451 47 non-elastic cross sections. Above 38 eV, the cross secitons 3440 1451 48 were calculated with POD code /1/. 3440 1451 49 3440 1451 50 MT= 2 Elastic scattering cross section 3440 1451 51 Below 38 eV, the cross sections were taken from JENDL-3.3 3440 1451 52 where the cross sections were estmated by assuming R = 7.1 fm.3440 1451 53 Above 38 eV, the cross sections were obtained by subtracitng 3440 1451 54 non-elastic cross sections from total cross sections. 3440 1451 55 3440 1451 56 MT= 3 Non-elastic cross section 3440 1451 57 Sum of partial non-elastic cross sections. 3440 1451 58 3440 1451 59 MT= 4,51-91 (n,n') cross section 3440 1451 60 Calculated with POD code /1/. 3440 1451 61 3440 1451 62 MT= 16 (n,2n) cross section 3440 1451 63 Calculated with POD code /1/. 3440 1451 64 3440 1451 65 MT= 17 (n,3n) cross section 3440 1451 66 Calculated with POD code /1/. 3440 1451 67 3440 1451 68 MT= 22 (n,na) cross section 3440 1451 69 Calculated with POD code /1/. 3440 1451 70 3440 1451 71 MT= 28 (n,np) cross section 3440 1451 72 Calculated with POD code /1/. 3440 1451 73 3440 1451 74 MT= 32 (n,nd) cross section 3440 1451 75 Calculated with POD code /1/. 3440 1451 76 3440 1451 77 MT=102 Capture cross section 3440 1451 78 Calculated with POD code /1/ above 38 eV. Below 38 eV, 3440 1451 79 the cross sections were taken from JENDL-3.3. The thermal 3440 1451 80 cross section was determined by the systematics of the Se 3440 1451 81 isotopes. 3440 1451 82 3440 1451 83 MT=103 (n,p) cross section 3440 1451 84 Calculated with POD code /1/. 3440 1451 85 3440 1451 86 MT=104 (n,d) cross section 3440 1451 87 Calculated with POD code /1/. 3440 1451 88 3440 1451 89 MT=105 (n,t) cross section 3440 1451 90 Calculated with POD code /1/. 3440 1451 91 3440 1451 92 MT=106 (n,He3) cross section 3440 1451 93 Calculated with POD code /1/. 3440 1451 94 3440 1451 95 MT=107 (n,a) cross section 3440 1451 96 Calculated with POD code /1/. 3440 1451 97 3440 1451 98 MT=203 (n,xp) cross section 3440 1451 99 Calculated with POD code /1/. 3440 1451 100 3440 1451 101 MT=204 (n,xd) cross section 3440 1451 102 Calculated with POD code /1/. 3440 1451 103 3440 1451 104 MT=205 (n,xt) cross section 3440 1451 105 Calculated with POD code /1/. 3440 1451 106 3440 1451 107 MT=206 (n,xHe3) cross section 3440 1451 108 Calculated with POD code /1/. 3440 1451 109 3440 1451 110 MT=207 (n,xa) cross section 3440 1451 111 Calculated with POD code /1/. 3440 1451 112 3440 1451 113 MF= 4 Angular distributions of emitted neutrons 3440 1451 114 MT= 2 Elastic scattering 3440 1451 115 Calculated with POD code /1/. 3440 1451 116 3440 1451 117 MF= 6 Energy-angle distributions of emitted particles 3440 1451 118 MT= 16 (n,2n) reaction 3440 1451 119 Neutron spectra calculated with POD/1/. 3440 1451 120 3440 1451 121 MT= 17 (n,3n) reaction 3440 1451 122 Neutron spectra calculated with POD/1/. 3440 1451 123 3440 1451 124 MT= 22 (n,na) reaction 3440 1451 125 Neutron spectra calculated with POD/1/. 3440 1451 126 3440 1451 127 MT= 28 (n,np) reaction 3440 1451 128 Neutron spectra calculated with POD/1/. 3440 1451 129 3440 1451 130 MT= 32 (n,nd) reaction 3440 1451 131 Neutron spectra calculated with POD/1/. 3440 1451 132 3440 1451 133 MT= 51 (n,n') reaction 3440 1451 134 Neutron angular distributions calculated with POD/1/. 3440 1451 135 3440 1451 136 MT= 52 (n,n') reaction 3440 1451 137 Neutron angular distributions calculated with POD/1/. 3440 1451 138 3440 1451 139 MT= 53 (n,n') reaction 3440 1451 140 Neutron angular distributions calculated with POD/1/. 3440 1451 141 3440 1451 142 MT= 54 (n,n') reaction 3440 1451 143 Neutron angular distributions calculated with POD/1/. 3440 1451 144 3440 1451 145 MT= 55 (n,n') reaction 3440 1451 146 Neutron angular distributions calculated with POD/1/. 3440 1451 147 3440 1451 148 MT= 56 (n,n') reaction 3440 1451 149 Neutron angular distributions calculated with POD/1/. 3440 1451 150 3440 1451 151 MT= 57 (n,n') reaction 3440 1451 152 Neutron angular distributions calculated with POD/1/. 3440 1451 153 3440 1451 154 MT= 58 (n,n') reaction 3440 1451 155 Neutron angular distributions calculated with POD/1/. 3440 1451 156 3440 1451 157 MT= 59 (n,n') reaction 3440 1451 158 Neutron angular distributions calculated with POD/1/. 3440 1451 159 3440 1451 160 MT= 60 (n,n') reaction 3440 1451 161 Neutron angular distributions calculated with POD/1/. 3440 1451 162 3440 1451 163 MT= 61 (n,n') reaction 3440 1451 164 Neutron angular distributions calculated with POD/1/. 3440 1451 165 3440 1451 166 MT= 62 (n,n') reaction 3440 1451 167 Neutron angular distributions calculated with POD/1/. 3440 1451 168 3440 1451 169 MT= 91 (n,n') reaction 3440 1451 170 Neutron spectra calculated with POD/1/. 3440 1451 171 3440 1451 172 MT= 203 (n,xp) reaction 3440 1451 173 Proton spectra calculated with POD/1/. 3440 1451 174 3440 1451 175 MT= 204 (n,xd) reaction 3440 1451 176 Deuteron spectra calculated with POD/1/. 3440 1451 177 3440 1451 178 MT= 205 (n,xt) reaction 3440 1451 179 Triton spectra calculated with POD/1/. 3440 1451 180 3440 1451 181 MT= 206 (n,xHe3) reaction 3440 1451 182 He3 spectra calculated with POD/1/. 3440 1451 183 3440 1451 184 MT= 207 (n,xa) reaction 3440 1451 185 Alpha spectra calculated with POD/1/. 3440 1451 186 3440 1451 187 MF=12 Gamma-ray multiplicities 3440 1451 188 MT= 3 Non-elastic gamma emission 3440 1451 189 Calculated with POD code /1/. 3440 1451 190 3440 1451 191 MF=14 Gamma-ray angular distributions 3440 1451 192 MT= 3 Non-elastic gamma emission 3440 1451 193 Assumed to be isotropic. 3440 1451 194 3440 1451 195 MF=15 Gamma-ray spectra 3440 1451 196 MT= 3 Non-elastic gamma emission 3440 1451 197 Calculated with POD code /1/. 3440 1451 198 3440 1451 199 3440 1451 200 3440 1451 201 *************************************************************** 3440 1451 202 * Nuclear Model Calculations with POD Code /1/ * 3440 1451 203 *************************************************************** 3440 1451 204 1. Theoretical models 3440 1451 205 The POD code is based on the spherical optical model, the 3440 1451 206 distorted-wave Born approximaiton (DWBA), one-component exciton 3440 1451 207 preequilibrium model, and the Hauser-Feshbach-Moldauer statis- 3440 1451 208 tical model. With the preequilibrim model, semi-empirical 3440 1451 209 pickup and knockout process can be taken into account for 3440 1451 210 composite-particle emission. The gamma-ray emission from the 3440 1451 211 compound nucleus can be calculated within the framework of the 3440 1451 212 exciton model. The code is capable of reading in particle 3440 1451 213 transmission coefficients calculated by separate spherical or 3440 1451 214 coupled-channel optical model code. 3440 1451 215 3440 1451 216 2. Optical model parameters 3440 1451 217 Neutrons: 3440 1451 218 Coupled-channel optical model parameters /2/ 3440 1451 219 Protons: 3440 1451 220 Koning and Delaroche /3/ 3440 1451 221 Deuterons: 3440 1451 222 Lohr and Haeberli /4/ 3440 1451 223 Tritons: 3440 1451 224 Becchetti and Greenlees /5/ 3440 1451 225 He-3: 3440 1451 226 Becchetti and Greenlees /5/ 3440 1451 227 Alphas: 3440 1451 228 Lemos /6/ potentials modified by Arthur and Young /7/ 3440 1451 229 3440 1451 230 3. Level scheme of Se- 79 3440 1451 231 ------------------------- 3440 1451 232 No. Ex(MeV) J PI 3440 1451 233 ------------------------- 3440 1451 234 0 0.00000 7/2 + 3440 1451 235 1 0.09577 1/2 - 3440 1451 236 2 0.12800 1/2 - 3440 1451 237 3 0.13697 9/2 + 3440 1451 238 4 0.36486 5/2 - 3440 1451 239 5 0.49900 3/2 - 3440 1451 240 6 0.52793 3/2 - 3440 1451 241 7 0.53400 5/2 + 3440 1451 242 8 0.57197 5/2 - 3440 1451 243 9 0.58600 3/2 + 3440 1451 244 10 0.62981 5/2 + 3440 1451 245 11 0.72250 1/2 - 3440 1451 246 12 0.72850 5/2 + 3440 1451 247 ------------------------- 3440 1451 248 Levels above 0.73850 MeV are assumed to be continuous. 3440 1451 249 3440 1451 250 4. Level density parameters 3440 1451 251 Energy-dependent parameters of Mengoni-Nakajima /8/ were used 3440 1451 252 ---------------------------------------------------------- 3440 1451 253 Nuclei a* Pair Esh T E0 Ematch Elv_max 3440 1451 254 1/MeV MeV MeV MeV MeV MeV MeV 3440 1451 255 ---------------------------------------------------------- 3440 1451 256 Se- 80 10.645 2.683 2.442 0.815 0.539 8.768 3.226 3440 1451 257 Se- 79 10.473 1.350 3.245 0.875 -1.656 8.768 0.729 3440 1451 258 Se- 78 9.830 2.717 3.184 0.927 -0.352 10.456 3.090 3440 1451 259 Se- 77 10.361 1.368 3.763 0.856 -1.590 8.612 1.511 3440 1451 260 As- 79 10.079 1.350 2.572 0.864 -0.976 7.886 1.518 3440 1451 261 As- 78 10.399 0.000 2.885 0.789 -1.940 5.686 0.536 3440 1451 262 As- 77 9.864 1.368 3.386 0.907 -1.622 8.902 1.676 3440 1451 263 Ge- 77 10.872 1.368 2.608 0.776 -0.625 7.045 1.385 3440 1451 264 Ge- 76 10.198 2.753 2.785 0.874 0.108 9.697 2.962 3440 1451 265 Ge- 75 9.958 1.386 3.393 0.852 -1.123 8.044 1.603 3440 1451 266 ---------------------------------------------------------- 3440 1451 267 3440 1451 268 5. Gamma-ray strength functions 3440 1451 269 M1, E2: Standard Lorentzian (SLO) 3440 1451 270 E1 : Generalized Lorentzian (GLO) /9/ 3440 1451 271 3440 1451 272 6. Preequilibrium process 3440 1451 273 Preequilibrium is on for n, p, d, t, He-3, and alpha. 3440 1451 274 Preequilibrium capture is on. 3440 1451 275 3440 1451 276 References 3440 1451 277 1) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 3440 1451 278 2) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 3440 1451 279 3) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 3440 1451 280 4) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 3440 1451 281 5) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization 3440 1451 282 Phenomena in Nuclear Reactions," p.682, The University 3440 1451 283 of Wisconsin Press (1971). 3440 1451 284 6) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 3440 1451 285 7) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 3440 1451 286 8) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 3440 1451 287 (1994). 3440 1451 288 9) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990). 3440 1451 289 3440 1451 290 1 451 316 13440 1451 291 2 151 4 13440 1451 292 3 4 21 13440 1451 293 3 16 9 13440 1451 294 3 17 5 13440 1451 295 3 22 7 13440 1451 296 3 28 7 13440 1451 297 3 32 5 13440 1451 298 3 102 116 13440 1451 299 3 103 12 13440 1451 300 3 104 8 13440 1451 301 3 105 7 13440 1451 302 3 106 6 13440 1451 303 3 107 13 13440 1451 304 8 4 2 13440 1451 305 8 16 2 13440 1451 306 8 17 2 13440 1451 307 8 22 2 13440 1451 308 8 28 2 13440 1451 309 8 32 2 13440 1451 310 8 102 2 13440 1451 311 8 103 2 13440 1451 312 8 104 2 13440 1451 313 8 105 2 13440 1451 314 8 106 2 13440 1451 315 8 107 2 13440 1451 316 3440 1 099999 3440 0 0 0 3.407900+4 7.824055+1 0 0 1 03440 2151 1 3.407900+4 1.000000+0 0 0 1 03440 2151 2 3.800000+1 5.000000+5 0 0 0 03440 2151 3 3.500000+0 6.333200-1 0 0 0 03440 2151 4 3440 2 099999 3440 0 0 0 3.407900+4 7.824055+1 0 0 0 03440 3 4 1 0.000000+0-9.577000+4 0 0 1 523440 3 4 2 52 2 3440 3 4 3 9.699405+4 0.000000+0 1.000000+5 0.000000+0 1.296360+5 2.837943-33440 3 4 4 1.387206+5 4.445741-3 2.000000+5 4.709910-1 3.000000+5 7.306900-13440 3 4 5 3.695233+5 8.191932-1 4.000000+5 1.007590+0 5.000000+5 1.191660+03440 3 4 6 5.053778+5 1.191330+0 5.346775+5 1.204363+0 5.408251+5 1.210550+03440 3 4 7 5.792804+5 1.307275+0 5.934897+5 1.384135+0 6.000000+5 1.422693+03440 3 4 8 6.378597+5 1.457212+0 7.000000+5 1.574320+0 7.317343+5 1.687075+03440 3 4 9 7.378110+5 1.708777+0 7.479388+5 1.752523+0 8.000000+5 1.977707+03440 3 4 10 9.000000+5 1.983535+0 1.000000+6 2.006471+0 1.500000+6 1.959535+03440 3 4 11 2.000000+6 1.995460+0 2.500000+6 2.021295+0 3.000000+6 2.078256+03440 3 4 12 3.500000+6 2.068908+0 4.000000+6 2.028152+0 4.500000+6 1.969645+03440 3 4 13 5.000000+6 1.914909+0 5.500000+6 1.870844+0 6.000000+6 1.837230+03440 3 4 14 6.500000+6 1.811959+0 7.000000+6 1.793077+0 7.500000+6 1.757128+03440 3 4 15 8.000000+6 1.665845+0 8.500000+6 1.500202+0 9.000000+6 1.319606+03440 3 4 16 9.500000+6 1.134213+0 1.000000+7 9.717636-1 1.100000+7 7.139358-13440 3 4 17 1.200000+7 5.572301-1 1.300000+7 4.661732-1 1.400000+7 4.042346-13440 3 4 18 1.450000+7 3.812571-1 1.500000+7 3.587204-1 1.600000+7 3.240778-13440 3 4 19 1.700000+7 2.955782-1 1.800000+7 2.718165-1 1.900000+7 2.519139-13440 3 4 20 2.000000+7 2.343445-1 3440 3 4 21 3440 3 099999 3.407900+4 7.824055+1 0 0 0 03440 3 16 1 -6.962832+6-6.962832+6 0 0 1 183440 3 16 2 18 2 3440 3 16 3 7.051824+6 0.000000+0 7.500000+6 2.122000-2 8.000000+6 1.005000-13440 3 16 4 8.500000+6 2.565000-1 9.000000+6 4.282000-1 9.500000+6 6.061000-13440 3 16 5 1.000000+7 7.606000-1 1.100000+7 1.003000+0 1.200000+7 1.144000+03440 3 16 6 1.300000+7 1.219000+0 1.400000+7 1.263000+0 1.450000+7 1.276000+03440 3 16 7 1.500000+7 1.287000+0 1.600000+7 1.298000+0 1.700000+7 1.299000+03440 3 16 8 1.800000+7 1.296000+0 1.900000+7 1.272000+0 2.000000+7 1.187000+03440 3 16 9 3440 3 099999 3.407900+4 7.824055+1 0 0 0 03440 3 17 1 -1.746064+7-1.746064+7 0 0 1 43440 3 17 2 4 2 3440 3 17 3 1.768381+7 0.000000+0 1.800000+7 0.000000+0 1.900000+7 1.809000-23440 3 17 4 2.000000+7 9.531000-2 3440 3 17 5 3440 3 099999 3.407900+4 7.824055+1 0 0 0 03440 3 22 1 -6.486090+6-6.486090+6 0 0 1 113440 3 22 2 11 2 3440 3 22 3 6.568989+6 0.000000+0 1.200000+7 0.000000+0 1.300000+7 1.135000-63440 3 22 4 1.400000+7 2.033000-5 1.450000+7 4.963000-5 1.500000+7 1.061000-43440 3 22 5 1.600000+7 3.500000-4 1.700000+7 7.861000-4 1.800000+7 1.329000-33440 3 22 6 1.900000+7 1.886000-3 2.000000+7 2.428000-3 3440 3 22 7 3440 3 099999 3.407900+4 7.824055+1 0 0 0 03440 3 28 1 -1.038915+7-1.038915+7 0 0 1 113440 3 28 2 11 2 3440 3 28 3 1.052194+7 0.000000+0 1.200000+7 0.000000+0 1.300000+7 4.617000-63440 3 28 4 1.400000+7 9.120000-5 1.450000+7 2.311000-4 1.500000+7 5.680000-43440 3 28 5 1.600000+7 1.990000-3 1.700000+7 4.857000-3 1.800000+7 9.459000-33440 3 28 6 1.900000+7 1.579000-2 2.000000+7 2.346000-2 3440 3 28 7 3440 3 099999 3.407900+4 7.824055+1 0 0 0 03440 3 32 1 -1.513675+7-1.513675+7 0 0 1 53440 3 32 2 5 2 3440 3 32 3 1.533021+7 0.000000+0 1.700000+7 0.000000+0 1.800000+7 2.714000-73440 3 32 4 1.900000+7 1.268000-5 2.000000+7 1.254000-4 3440 3 32 5 3440 3 099999 3.407900+4 7.824055+1 0 0 0 03440 3102 1 9.913651+6 9.913651+6 0 0 1 3383440 3102 2 338 2 3440 3102 3 1.000000-5 2.514999+3 1.103037-5 2.394654+3 1.216691-5 2.280068+33440 3102 4 1.342055-5 2.170965+3 1.480336-5 2.067082+3 1.632865-5 1.968171+33440 3102 5 1.801111-5 1.873992+3 1.986691-5 1.784320+3 2.191394-5 1.698938+33440 3102 6 2.417189-5 1.617643+3 2.666248-5 1.540237+3 2.940971-5 1.466535+33440 3102 7 3.243999-5 1.396360+3 3.578251-5 1.329543+3 3.946943-5 1.265923+33440 3102 8 4.353624-5 1.205348+3 4.802208-5 1.147671+3 5.297013-5 1.092754+33440 3102 9 5.842801-5 1.040464+3 6.444825-5 9.906773+2 7.108881-5 9.432725+23440 3102 10 7.841358-5 8.981360+2 8.649308-5 8.551594+2 9.540506-5 8.142393+23440 3102 11 1.052353-4 7.752772+2 1.160784-4 7.381794+2 1.280388-4 7.028569+23440 3102 12 1.412315-4 6.692245+2 1.557836-4 6.372015+2 1.718351-4 6.067108+23440 3102 13 1.895404-4 5.776791+2 2.090701-4 5.500366+2 2.306120-4 5.237168+23440 3102 14 2.543736-4 4.986565+2 2.805835-4 4.747953+2 3.094939-4 4.520759+23440 3102 15 3.413832-4 4.304436+2 3.765583-4 4.098465+2 4.153577-4 3.902349+23440 3102 16 4.581549-4 3.715618+2 5.053618-4 3.537822+2 5.574328-4 3.368533+23440 3102 17 6.148689-4 3.207346+2 6.782232-4 3.053871+2 7.481052-4 2.907740+23440 3102 18 8.251877-4 2.768602+2 9.102125-4 2.636121+2 1.003998-3 2.509980+23440 3102 19 1.107447-3 2.389875+2 1.221555-3 2.275517+2 1.347420-3 2.166631+23440 3102 20 1.486254-3 2.062955+2 1.639393-3 1.964241+2 1.808311-3 1.870250+23440 3102 21 1.994634-3 1.780756+2 2.200155-3 1.695545+2 2.426853-3 1.614411+23440 3102 22 2.676908-3 1.537160+2 2.952729-3 1.463605+2 3.256969-3 1.393570+23440 3102 23 3.592557-3 1.326886+2 3.962723-3 1.263393+2 4.371030-3 1.202939+23440 3102 24 4.821407-3 1.145377+2 5.318191-3 1.090570+2 5.866161-3 1.038385+23440 3102 25 6.470592-3 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