JENDL-5 (Neutron sublibrary (activation cs)) Bk-247 0 0 0 0 9.724700+4 2.449480+2 0 0 6 19746 1451 1 0.000000+0 1.000000+0 0 0 0 69746 1451 2 1.000000+0 2.000000+7 0 0 10 59746 1451 3 2.936000+2 0.000000+0 4 0 317 149746 1451 4 97-Bk-247 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9746 1451 5 DIST-DEC21 20100304 9746 1451 6 ----JENDL-5 MATERIAL 9746 9746 1451 7 -----INCIDENT NEUTRON DATA 9746 1451 8 ------ENDF-6 FORMAT 9746 1451 9 9746 1451 10 History 9746 1451 11 07-09 Theoretical calculation was performed with CCONE code. 9746 1451 12 07-10 Re-calculation with CCONE code was done. 9746 1451 13 07-12 Data were compiled as JENDL/AC-2008/1/. 9746 1451 14 10-02 Data of prompt gamma rays due to fission were given. 9746 1451 15 10-03 Covariance data were given. 9746 1451 16 9746 1451 17 21-11 revised by O.Iwamoto 9746 1451 18 (MF3/MT19-21,38) deleted 9746 1451 19 (MF8/MT4,16-18,37,102) added 9746 1451 20 9746 1451 21 MF=1 General information 9746 1451 22 MT=452 Number of Neutrons per fission 9746 1451 23 Sum of MT's=455 and 456. 9746 1451 24 9746 1451 25 MT=455 Delayed neutron data 9746 1451 26 (Same as JENDL-3.3) 9746 1451 27 Estimated from Tuttle's systematics/2/. 9746 1451 28 9746 1451 29 MT=456 Number of prompt neutrons per fission 9746 1451 30 (Same as JENDL-3.3) 9746 1451 31 Estimated from Howerton's sytematics/3/. 9746 1451 32 9746 1451 33 9746 1451 34 MF= 2 Resonance parameters 9746 1451 35 MT=151 9746 1451 36 No resonance parameters are given. 9746 1451 37 9746 1451 38 9746 1451 39 Thermal cross sections and resonance integrals (at 300K) 9746 1451 40 ------------------------------------------------------- 9746 1451 41 0.0253 eV reson. integ.(*) 9746 1451 42 (barns) (barns) 9746 1451 43 ------------------------------------------------------- 9746 1451 44 total 1014.5 9746 1451 45 elastic 10.12 9746 1451 46 fission 3.70 4.97 9746 1451 47 capture 1000.4 837 9746 1451 48 ------------------------------------------------------- 9746 1451 49 (*) In the energy range from 0.5 eV to 10 MeV. 9746 1451 50 9746 1451 51 9746 1451 52 MF= 3 Neutron cross sections 9746 1451 53 Below 1.0 eV: 9746 1451 54 * Elastic scattering cross section is 10.1 b calculated from 9746 1451 55 scattering radius of 8.955 fm/4/. 9746 1451 56 * Fission cross section is extrapolation of CCONE calculation.9746 1451 57 * Capture cross section is 1000 b at 0.0253 eV which was 9746 1451 58 estimated from systematics. 9746 1451 59 9746 1451 60 Above 1.0 eV: 9746 1451 61 Cross sections were calculated with CCONE code/4/. 9746 1451 62 9746 1451 63 MT= 1 Total cross section 9746 1451 64 The cross section was calculated with CC OMP of Soukhovitskii 9746 1451 65 et al./5/ 9746 1451 66 9746 1451 67 MT=18 Fission cross section 9746 1451 68 The simulated (n,f) cross sections of Britt and Wilhelmy/6/ 9746 1451 69 were used to determine the parameters in the CCONE 9746 1451 70 calculation. 9746 1451 71 9746 1451 72 9746 1451 73 MF= 4 Angular distributions of secondary neutrons 9746 1451 74 MT=2 Elastic scattering 9746 1451 75 Calculated with CCONE code/4/. 9746 1451 76 9746 1451 77 MT=18 Fission 9746 1451 78 Isotropic distributions in the laboratory system were assumed.9746 1451 79 9746 1451 80 9746 1451 81 MF= 5 Energy distributions of secondary neutrons 9746 1451 82 MT=18 Prompt neutrons 9746 1451 83 Calculated with CCONE code/4/. 9746 1451 84 9746 1451 85 9746 1451 86 MF= 6 Energy-angle distributions 9746 1451 87 Calculated with CCONE code/4/. 9746 1451 88 Distributions from fission (MT=18) are not included. 9746 1451 89 9746 1451 90 9746 1451 91 MF=12 Photon production multiplicities 9746 1451 92 MT=18 Fission 9746 1451 93 Calculated from the total energy released by the prompt 9746 1451 94 gamma-rays due to fission which was estimated from its 9746 1451 95 systematics, and the average energy of gamma-rays. 9746 1451 96 9746 1451 97 9746 1451 98 MF=14 Photon angular distributions 9746 1451 99 MT=18 Fission 9746 1451 100 Isotoropic distributions were assumed. 9746 1451 101 9746 1451 102 9746 1451 103 MF=15 Continuous photon energy spectra 9746 1451 104 MT=18 Fission 9746 1451 105 Experimental data measured by Verbinski et al./7/ for 9746 1451 106 Pu-239 thermal fission were adopted. 9746 1451 107 9746 1451 108 9746 1451 109 MF=31 Covariances of average number of neutrons per fission 9746 1451 110 MT=452 Number of neutrons per fission 9746 1451 111 Sum of covariances for MT=455 and MT=456. 9746 1451 112 9746 1451 113 MT=455 9746 1451 114 Error of 15% was assumed. 9746 1451 115 9746 1451 116 MT=456 9746 1451 117 Covariance was obtained by fitting a linear function to the 9746 1451 118 at 0.0 and 5.0 MeV with an uncertainty of 10%. 9746 1451 119 9746 1451 120 9746 1451 121 MF=33 Covariances of neutron cross sections 9746 1451 122 Covariances were given to all the cross sections by using 9746 1451 123 KALMAN code/8/ and the covariances of model parameters 9746 1451 124 used in the cross-section calculations. 9746 1451 125 9746 1451 126 Covariances of the fission cross section were determined from 9746 1451 127 experimental data. 9746 1451 128 9746 1451 129 For the following cross sections, standard deviations in the 9746 1451 130 energy region below 1.0 eV were assumed as follows: 9746 1451 131 9746 1451 132 Total 49 % 9746 1451 133 Elastic scattering 50 % 9746 1451 134 Fission 50 % 9746 1451 135 Capture 50 % 9746 1451 136 9746 1451 137 9746 1451 138 MF=34 Covariances for Angular Distributions 9746 1451 139 MT=2 Elastic scattering 9746 1451 140 Covariances were given only to P1 components. 9746 1451 141 9746 1451 142 9746 1451 143 MF=35 Covariances for Energy Distributions 9746 1451 144 MT=18 Fission spectra 9746 1451 145 Estimated with CCONE and KALMAN codes. 9746 1451 146 9746 1451 147 9746 1451 148 ***************************************************************** 9746 1451 149 Calculation with CCONE code 9746 1451 150 ***************************************************************** 9746 1451 151 9746 1451 152 Models and parameters used in the CCONE/4/ calculation 9746 1451 153 1) Coupled channel optical model 9746 1451 154 Levels in the rotational band were included. Optical model 9746 1451 155 potential and coupled levels are shown in Table 1. 9746 1451 156 9746 1451 157 2) Two-component exciton model/9/ 9746 1451 158 * Global parametrization of Koning-Duijvestijn/10/ 9746 1451 159 was used. 9746 1451 160 * Gamma emission channel/11/ was added to simulate direct 9746 1451 161 and semi-direct capture reaction. 9746 1451 162 9746 1451 163 3) Hauser-Feshbach statistical model 9746 1451 164 * Moldauer width fluctuation correction/12/ was included. 9746 1451 165 * Neutron, gamma and fission decay channel were included. 9746 1451 166 * Transmission coefficients of neutrons were taken from 9746 1451 167 coupled channel calculation in Table 1. 9746 1451 168 * The level scheme of the target is shown in Table 2. 9746 1451 169 * Level density formula of constant temperature and Fermi-gas 9746 1451 170 model were used with shell energy correction and collective 9746 1451 171 enhancement factor. Parameters are shown in Table 3. 9746 1451 172 * Fission channel: 9746 1451 173 Double humped fission barriers were assumed. 9746 1451 174 Fission barrier penetrabilities were calculated with 9746 1451 175 Hill-Wheler formula/13/. Fission barrier parameters were 9746 1451 176 shown in Table 4. Transition state model was used and 9746 1451 177 continuum levels are assumed above the saddles. The level 9746 1451 178 density parameters for inner and outer saddles are shown in 9746 1451 179 Tables 5 and 6, respectively. 9746 1451 180 * Gamma-ray strength function of Kopecky et al/14/,/15/ 9746 1451 181 was used. The prameters are shown in Table 7. 9746 1451 182 9746 1451 183 9746 1451 184 ------------------------------------------------------------------9746 1451 185 Tables 9746 1451 186 ------------------------------------------------------------------9746 1451 187 9746 1451 188 Table 1. Coupled channel calculation 9746 1451 189 -------------------------------------------------- 9746 1451 190 * rigid rotor model was applied 9746 1451 191 * coupled levels = 0,1,3,5 (see Table 2) 9746 1451 192 * optical potential parameters /5/ 9746 1451 193 Volume: 9746 1451 194 V_0 = 49.97 MeV 9746 1451 195 lambda_HF = 0.01004 1/MeV 9746 1451 196 C_viso = 15.9 MeV 9746 1451 197 A_v = 12.04 MeV 9746 1451 198 B_v = 81.36 MeV 9746 1451 199 E_a = 385 MeV 9746 1451 200 r_v = 1.2568 fm 9746 1451 201 a_v = 0.633 fm 9746 1451 202 Surface: 9746 1451 203 W_0 = 17.2 MeV 9746 1451 204 B_s = 11.19 MeV 9746 1451 205 C_s = 0.01361 1/MeV 9746 1451 206 C_wiso = 23.5 MeV 9746 1451 207 r_s = 1.1803 fm 9746 1451 208 a_s = 0.601 fm 9746 1451 209 Spin-orbit: 9746 1451 210 V_so = 5.75 MeV 9746 1451 211 lambda_so = 0.005 1/MeV 9746 1451 212 W_so = -3.1 MeV 9746 1451 213 B_so = 160 MeV 9746 1451 214 r_so = 1.1214 fm 9746 1451 215 a_so = 0.59 fm 9746 1451 216 Coulomb: 9746 1451 217 C_coul = 1.3 9746 1451 218 r_c = 1.2452 fm 9746 1451 219 a_c = 0.545 fm 9746 1451 220 Deformation: 9746 1451 221 beta_2 = 0.213 9746 1451 222 beta_4 = 0.066 9746 1451 223 beta_6 = 0.0015 9746 1451 224 9746 1451 225 * Calculated strength function 9746 1451 226 S0= 0.90e-4 S1= 3.90e-4 R'= 8.95 fm (En=1 keV) 9746 1451 227 -------------------------------------------------- 9746 1451 228 9746 1451 229 Table 2. Level Scheme of Bk-247 9746 1451 230 ------------------- 9746 1451 231 No. Ex(MeV) J PI 9746 1451 232 ------------------- 9746 1451 233 0 0.00000 3/2 - * 9746 1451 234 1 0.02990 5/2 - * 9746 1451 235 2 0.04080 7/2 + 9746 1451 236 3 0.07160 7/2 - * 9746 1451 237 4 0.08280 9/2 + 9746 1451 238 5 0.12550 9/2 - * 9746 1451 239 6 0.13700 11/2 + 9746 1451 240 7 0.19600 13/2 + 9746 1451 241 8 0.26500 15/2 + 9746 1451 242 ------------------- 9746 1451 243 *) Coupled levels in CC calculation 9746 1451 244 9746 1451 245 Table 3. Level density parameters 9746 1451 246 -------------------------------------------------------- 9746 1451 247 Nuclide a* Pair Eshell T E0 Ematch 9746 1451 248 1/MeV MeV MeV MeV MeV MeV 9746 1451 249 -------------------------------------------------------- 9746 1451 250 Bk-248 19.0305 0.0000 1.2435 0.2843 -0.6878 1.0000 9746 1451 251 Bk-247 18.9645 0.7635 1.3193 0.3836 -0.7996 2.9113 9746 1451 252 Bk-246 18.8984 0.0000 0.9401 0.2886 -0.6877 1.0000 9746 1451 253 Bk-245 18.8322 0.7667 1.2089 0.4136 -1.0946 3.2897 9746 1451 254 Bk-244 18.7661 0.0000 1.0000 0.2893 -0.6864 1.0000 9746 1451 255 -------------------------------------------------------- 9746 1451 256 9746 1451 257 Table 4. Fission barrier parameters 9746 1451 258 ---------------------------------------- 9746 1451 259 Nuclide V_A hw_A V_B hw_B 9746 1451 260 MeV MeV MeV MeV 9746 1451 261 ---------------------------------------- 9746 1451 262 Bk-248 6.750 0.700 6.300 0.600 9746 1451 263 Bk-247 6.300 0.800 5.970 0.520 9746 1451 264 Bk-246 6.200 0.650 6.600 0.500 9746 1451 265 Bk-245 6.300 0.800 5.970 0.520 9746 1451 266 Bk-244 6.200 0.650 5.550 0.450 9746 1451 267 ---------------------------------------- 9746 1451 268 9746 1451 269 Table 5. Level density above inner saddle 9746 1451 270 -------------------------------------------------------- 9746 1451 271 Nuclide a* Pair Eshell T E0 Ematch 9746 1451 272 1/MeV MeV MeV MeV MeV MeV 9746 1451 273 -------------------------------------------------------- 9746 1451 274 Bk-248 21.3142 0.0000 2.6000 0.3218 -2.4112 2.0000 9746 1451 275 Bk-247 21.2402 0.8908 2.6000 0.2836 -0.9848 2.3908 9746 1451 276 Bk-246 21.1662 0.0000 2.6000 0.3230 -2.4113 2.0000 9746 1451 277 Bk-245 21.0921 0.8944 2.6000 0.2846 -0.9813 2.3944 9746 1451 278 Bk-244 21.0180 0.0000 2.6000 0.3242 -2.4113 2.0000 9746 1451 279 -------------------------------------------------------- 9746 1451 280 9746 1451 281 Table 6. Level density above outer saddle 9746 1451 282 -------------------------------------------------------- 9746 1451 283 Nuclide a* Pair Eshell T E0 Ematch 9746 1451 284 1/MeV MeV MeV MeV MeV MeV 9746 1451 285 -------------------------------------------------------- 9746 1451 286 Bk-248 22.4560 0.0000 0.9200 0.3265 -1.5297 1.8000 9746 1451 287 Bk-247 24.6538 0.8908 0.8800 0.2869 -0.3705 2.3908 9746 1451 288 Bk-246 21.3551 0.0000 0.8400 0.3594 -1.7906 2.1000 9746 1451 289 Bk-245 24.4819 0.8944 0.8000 0.2888 -0.3662 2.3944 9746 1451 290 Bk-244 21.0180 0.0000 0.7600 0.3563 -1.7065 2.0000 9746 1451 291 -------------------------------------------------------- 9746 1451 292 9746 1451 293 Table 7. Gamma-ray strength function for Bk-248 9746 1451 294 -------------------------------------------------------- 9746 1451 295 K0 = 1.500 E0 = 4.500 (MeV) 9746 1451 296 * E1: ER = 11.40 (MeV) EG = 2.71 (MeV) SIG = 252.04 (mb) 9746 1451 297 ER = 14.30 (MeV) EG = 4.18 (MeV) SIG = 504.08 (mb) 9746 1451 298 * M1: ER = 6.53 (MeV) EG = 4.00 (MeV) SIG = 1.79 (mb) 9746 1451 299 * E2: ER = 10.03 (MeV) EG = 3.13 (MeV) SIG = 7.21 (mb) 9746 1451 300 -------------------------------------------------------- 9746 1451 301 9746 1451 302 9746 1451 303 References 9746 1451 304 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9746 1451 305 2) R.J.Tuttld: INDC(NDS)-107/G+Special, p.29 (1979). 9746 1451 306 3) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9746 1451 307 4) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9746 1451 308 5) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9746 1451 309 6) H.C.Britt, J.B.Wilhelmy: Nucl. Sci. Eng., 72, 222 (1979). 9746 1451 310 7) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9746 1451 311 8) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9746 1451 312 Japanese. 9746 1451 313 9) C.Kalbach: Phys. Rev. C33, 818 (1986). 9746 1451 314 10) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9746 1451 315 11) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9746 1451 316 12) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9746 1451 317 13) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9746 1451 318 14) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9746 1451 319 15) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9746 1451 320 9746 1451 321 1 451 335 19746 1451 322 2 151 4 19746 1451 323 3 4 28 19746 1451 324 3 16 13 19746 1451 325 3 17 9 19746 1451 326 3 18 132 19746 1451 327 3 37 4 19746 1451 328 3 102 156 19746 1451 329 8 4 2 19746 1451 330 8 16 2 19746 1451 331 8 17 2 19746 1451 332 8 18 2 19746 1451 333 8 37 2 19746 1451 334 8 102 2 19746 1451 335 9746 1 099999 9746 0 0 0 9.724700+4 2.449480+2 0 0 1 09746 2151 1 9.724700+4 1.000000+0 0 0 1 09746 2151 2 1.000000-5 1.000000+0 0 0 0 09746 2151 3 1.500000+0 8.955000-1 0 0 0 09746 2151 4 9746 2 099999 9746 0 0 0 9.724700+4 2.449480+2 0 0 0 09746 3 4 1 0.000000+0-2.990000+4 0 0 1 749746 3 4 2 74 2 9746 3 4 3 3.002210+4 0.000000+0 4.096660+4 2.286070-1 5.000000+4 4.342146-19746 3 4 4 7.000000+4 7.016540-1 7.189230+4 7.216350-1 8.313800+4 8.602249-19746 3 4 5 1.000000+5 1.057571+0 1.109000+5 1.144276+0 1.200000+5 1.216687+09746 3 4 6 1.260120+5 1.259045+0 1.375590+5 1.334844+0 1.400000+5 1.349962+09746 3 4 7 1.700000+5 1.519275+0 1.968000+5 1.655516+0 2.000000+5 1.671368+09746 3 4 8 2.500000+5 1.801659+0 2.660820+5 1.839848+0 3.000000+5 1.920726+09746 3 4 9 4.000000+5 2.107429+0 5.000000+5 2.440351+0 6.000000+5 2.687572+09746 3 4 10 7.000000+5 2.919424+0 8.000000+5 3.052817+0 9.000000+5 3.136140+09746 3 4 11 1.000000+6 3.175405+0 1.100000+6 3.154065+0 1.200000+6 3.108371+09746 3 4 12 1.300000+6 3.058294+0 1.400000+6 3.023092+0 1.500000+6 2.988959+09746 3 4 13 1.600000+6 2.963294+0 1.700000+6 2.929649+0 1.800000+6 2.897761+09746 3 4 14 1.900000+6 2.856169+0 2.000000+6 2.814084+0 2.100000+6 2.764211+09746 3 4 15 2.300000+6 2.661613+0 2.500000+6 2.552880+0 2.700000+6 2.446430+09746 3 4 16 3.000000+6 2.297851+0 3.500000+6 2.126569+0 4.000000+6 1.991536+09746 3 4 17 4.500000+6 1.910798+0 5.000000+6 1.848869+0 5.500000+6 1.813456+09746 3 4 18 6.000000+6 1.777953+0 6.500000+6 1.610439+0 7.000000+6 1.346015+09746 3 4 19 7.500000+6 1.077411+0 8.000000+6 8.738241-1 8.500000+6 7.286608-19746 3 4 20 9.000000+6 6.345584-1 9.500000+6 5.711611-1 1.000000+7 5.296580-19746 3 4 21 1.050000+7 4.970865-1 1.100000+7 4.723867-1 1.150000+7 4.522763-19746 3 4 22 1.200000+7 4.334895-1 1.250000+7 4.171956-1 1.300000+7 4.013921-19746 3 4 23 1.350000+7 3.868959-1 1.400000+7 3.724721-1 1.450000+7 3.599038-19746 3 4 24 1.500000+7 3.467185-1 1.550000+7 3.353451-1 1.600000+7 3.240259-19746 3 4 25 1.650000+7 3.131830-1 1.700000+7 3.031052-1 1.750000+7 2.940210-19746 3 4 26 1.800000+7 2.850491-1 1.850000+7 2.769683-1 1.900000+7 2.690017-19746 3 4 27 1.950000+7 2.617911-1 2.000000+7 2.546807-1 9746 3 4 28 9746 3 099999 9.724700+4 2.449480+2 0 0 0 09746 3 16 1 -6.549130+6-6.549130+6 0 0 1 289746 3 16 2 28 2 9746 3 16 3 6.575870+6 0.000000+0 7.000000+6 2.478290-2 7.500000+6 1.675440-19746 3 16 4 8.000000+6 3.345430-1 8.500000+6 4.601320-1 9.000000+6 5.344050-19746 3 16 5 9.500000+6 5.607100-1 1.000000+7 5.511980-1 1.050000+7 5.378380-19746 3 16 6 1.100000+7 5.127610-1 1.150000+7 4.825670-1 1.200000+7 4.580550-19746 3 16 7 1.250000+7 4.324380-1 1.300000+7 4.091220-1 1.350000+7 3.852490-19746 3 16 8 1.400000+7 3.567760-1 1.450000+7 3.216120-1 1.500000+7 2.893540-19746 3 16 9 1.550000+7 2.560940-1 1.600000+7 2.304290-1 1.650000+7 2.099540-19746 3 16 10 1.700000+7 1.931170-1 1.750000+7 1.796550-1 1.800000+7 1.688040-19746 3 16 11 1.850000+7 1.601170-1 1.900000+7 1.529220-1 1.950000+7 1.467990-19746 3 16 12 2.000000+7 1.430500-1 9746 3 16 13 9746 3 099999 9.724700+4 2.449480+2 0 0 0 09746 3 17 1 -1.246750+7-1.246750+7 0 0 1 169746 3 17 2 16 2 9746 3 17 3 1.251840+7 0.000000+0 1.300000+7 2.031800-4 1.350000+7 4.063950-39746 3 17 4 1.400000+7 1.344970-2 1.450000+7 2.564350-2 1.500000+7 3.834790-29746 3 17 5 1.550000+7 4.979590-2 1.600000+7 5.413890-2 1.650000+7 6.099130-29746 3 17 6 1.700000+7 6.141860-2 1.750000+7 6.099580-2 1.800000+7 5.997550-29746 3 17 7 1.850000+7 5.876570-2 1.900000+7 5.764080-2 1.950000+7 5.676240-29746 3 17 8 2.000000+7 5.384880-2 9746 3 17 9 9746 3 099999 9.724700+4 2.449480+2 0 0 0 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