JENDL-5 (Neutron sublibrary (activation cs)) Bk-250 0 0 0 0 9.725000+4 2.479300+2 0 0 6 19755 1451 1 0.000000+0 1.000000+0 0 0 0 69755 1451 2 1.000000+0 2.000000+7 0 0 10 59755 1451 3 2.936000+2 0.000000+0 4 0 325 149755 1451 4 97-Bk-250 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9755 1451 5 DIST-DEC21 20100303 9755 1451 6 ----JENDL-5 MATERIAL 9755 9755 1451 7 -----INCIDENT NEUTRON DATA 9755 1451 8 ------ENDF-6 FORMAT 9755 1451 9 9755 1451 10 History 9755 1451 11 07-09 Theoretical calculation was performed with CCONE code. 9755 1451 12 Data were compiled as JENDL/AC-2008/1/. 9755 1451 13 10-02 Data of prompt gamma rays due to fission were given. 9755 1451 14 10-03 Covariance data were given. 9755 1451 15 21-11 revised by O.Iwamoto 9755 1451 16 (MF3/MT19-21,38) deleted 9755 1451 17 (MF8/MT4,16-18,37,102) added 9755 1451 18 9755 1451 19 9755 1451 20 MF=1 General information 9755 1451 21 MT=452 Number of Neutrons per fission 9755 1451 22 Sum of MT's=455 and 456. 9755 1451 23 9755 1451 24 MT=455 Delayed neutron data 9755 1451 25 (Same as JENDL-3.3) 9755 1451 26 Estimated from Tuttle's systematics/2/. 9755 1451 27 9755 1451 28 MT=456 Number of prompt neutrons per fission 9755 1451 29 (Same as JENDL-3.3) 9755 1451 30 Estimated from Howerton's sytematics/3/. 9755 1451 31 9755 1451 32 9755 1451 33 MF= 2 Resonance parameters 9755 1451 34 MT=151 9755 1451 35 No resonance parameters are given. 9755 1451 36 9755 1451 37 9755 1451 38 Thermal cross sections and resonance integrals (at 300K) 9755 1451 39 ------------------------------------------------------- 9755 1451 40 0.0253 eV reson. integ.(*) 9755 1451 41 (barns) (barns) 9755 1451 42 ------------------------------------------------------- 9755 1451 43 total 1771.1 9755 1451 44 elastic 9.72 9755 1451 45 fission 980.6 623 9755 1451 46 capture 780.5 492 9755 1451 47 ------------------------------------------------------- 9755 1451 48 (*) In the energy range from 0.5 eV to 10 MeV. 9755 1451 49 9755 1451 50 9755 1451 51 MF= 3 Neutron cross sections 9755 1451 52 Below 0.4 eV: 9755 1451 53 * Elastic scattering cross section is 9.7 b calculated from 9755 1451 54 scattering radius of 8.779 fm/4/. 9755 1451 55 * Fission cross section is in the 1/v shape, and 980 b at 9755 1451 56 0.0253 eV which was obtained from the data of 960+-150 b 9755 1451 57 measured by Diamond et al./5/ and renormalized to the 9755 1451 58 current U-235 fission cross section. 9755 1451 59 * Capture cross section is in the 1/v shape, and 780 b at 9755 1451 60 0.0253 eV which was estimated by assuming that the cross- 9755 1451 61 section ratio of capture and fission was the same as that 9755 1451 62 at 1 eV calculated with CCONE code/4/. 9755 1451 63 9755 1451 64 Above 0.4 eV: 9755 1451 65 Cross sections were calculated with CCONE code/4/. 9755 1451 66 9755 1451 67 MT= 1 Total cross section 9755 1451 68 The cross section was calculated with CC OMP of Soukhovitskii 9755 1451 69 et al./6/ 9755 1451 70 9755 1451 71 9755 1451 72 MF= 4 Angular distributions of secondary neutrons 9755 1451 73 MT=2 Elastic scattering 9755 1451 74 Calculated with CCONE code/4/. 9755 1451 75 9755 1451 76 MT=18 Fission 9755 1451 77 Isotropic distributions in the laboratory system were assumed.9755 1451 78 9755 1451 79 9755 1451 80 MF= 5 Energy distributions of secondary neutrons 9755 1451 81 MT=18 Prompt neutrons 9755 1451 82 Calculated with CCONE code/4/. 9755 1451 83 9755 1451 84 9755 1451 85 MF= 6 Energy-angle distributions 9755 1451 86 Calculated with CCONE code/4/. 9755 1451 87 Distributions from fission (MT=18) are not included. 9755 1451 88 9755 1451 89 9755 1451 90 MF=12 Photon production multiplicities 9755 1451 91 MT=18 Fission 9755 1451 92 Calculated from the total energy released by the prompt 9755 1451 93 gamma-rays due to fission which was estimated from its 9755 1451 94 systematics, and the average energy of gamma-rays. 9755 1451 95 9755 1451 96 9755 1451 97 MF=14 Photon angular distributions 9755 1451 98 MT=18 Fission 9755 1451 99 Isotoropic distributions were assumed. 9755 1451 100 9755 1451 101 9755 1451 102 MF=15 Continuous photon energy spectra 9755 1451 103 MT=18 Fission 9755 1451 104 Experimental data measured by Verbinski et al./7/ for 9755 1451 105 Pu-239 thermal fission were adopted. 9755 1451 106 9755 1451 107 9755 1451 108 MF=31 Covariances of average number of neutrons per fission 9755 1451 109 MT=452 Number of neutrons per fission 9755 1451 110 Sum of covariances for MT=455 and MT=456. 9755 1451 111 9755 1451 112 MT=455 9755 1451 113 Error of 15% was assumed. 9755 1451 114 9755 1451 115 MT=456 9755 1451 116 Covariance was obtained by fitting a linear function to the 9755 1451 117 at 0.0 and 5.0 MeV with an uncertainty of 10%. 9755 1451 118 9755 1451 119 9755 1451 120 MF=33 Covariances of neutron cross sections 9755 1451 121 Covariances were given to all the cross sections by using 9755 1451 122 KALMAN code/8/ and the covariances of model parameters 9755 1451 123 used in the cross-section calculations. 9755 1451 124 9755 1451 125 For the following cross sections, standard deviations in the 9755 1451 126 energy region below 0.4 eV were assumed as follows: 9755 1451 127 9755 1451 128 Total 24 % 9755 1451 129 Elastic scattering 50 % 9755 1451 130 Fission 19 % estimated from experimental data 9755 1451 131 Capture 50 % 9755 1451 132 9755 1451 133 9755 1451 134 MF=34 Covariances for Angular Distributions 9755 1451 135 MT=2 Elastic scattering 9755 1451 136 Covariances were given only to P1 components. 9755 1451 137 9755 1451 138 9755 1451 139 MF=35 Covariances for Energy Distributions 9755 1451 140 MT=18 Fission spectra 9755 1451 141 Estimated with CCONE and KALMAN codes. 9755 1451 142 9755 1451 143 9755 1451 144 ***************************************************************** 9755 1451 145 Calculation with CCONE code 9755 1451 146 ***************************************************************** 9755 1451 147 9755 1451 148 Models and parameters used in the CCONE/4/ calculation 9755 1451 149 1) Coupled channel optical model 9755 1451 150 Levels in the rotational band were included. Optical model 9755 1451 151 potential and coupled levels are shown in Table 1. 9755 1451 152 9755 1451 153 2) Two-component exciton model/9/ 9755 1451 154 * Global parametrization of Koning-Duijvestijn/10/ 9755 1451 155 was used. 9755 1451 156 * Gamma emission channel/11/ was added to simulate direct 9755 1451 157 and semi-direct capture reaction. 9755 1451 158 9755 1451 159 3) Hauser-Feshbach statistical model 9755 1451 160 * Moldauer width fluctuation correction/12/ was included. 9755 1451 161 * Neutron, gamma and fission decay channel were included. 9755 1451 162 * Transmission coefficients of neutrons were taken from 9755 1451 163 coupled channel calculation in Table 1. 9755 1451 164 * The level scheme of the target is shown in Table 2. 9755 1451 165 * Level density formula of constant temperature and Fermi-gas 9755 1451 166 model were used with shell energy correction and collective 9755 1451 167 enhancement factor. Parameters are shown in Table 3. 9755 1451 168 * Fission channel: 9755 1451 169 Double humped fission barriers were assumed. 9755 1451 170 Fission barrier penetrabilities were calculated with 9755 1451 171 Hill-Wheler formula/13/. Fission barrier parameters were 9755 1451 172 shown in Table 4. Transition state model was used and 9755 1451 173 continuum levels are assumed above the saddles. The level 9755 1451 174 density parameters for inner and outer saddles are shown in 9755 1451 175 Tables 5 and 6, respectively. 9755 1451 176 * Gamma-ray strength function of Kopecky et al/14/,/15/ 9755 1451 177 was used. The prameters are shown in Table 7. 9755 1451 178 9755 1451 179 9755 1451 180 ------------------------------------------------------------------9755 1451 181 Tables 9755 1451 182 ------------------------------------------------------------------9755 1451 183 9755 1451 184 Table 1. Coupled channel calculation 9755 1451 185 -------------------------------------------------- 9755 1451 186 * rigid rotor model was applied 9755 1451 187 * coupled levels = 0,1,4,11 (see Table 2) 9755 1451 188 * optical potential parameters /6/ 9755 1451 189 Volume: 9755 1451 190 V_0 = 49.97 MeV 9755 1451 191 lambda_HF = 0.01004 1/MeV 9755 1451 192 C_viso = 15.9 MeV 9755 1451 193 A_v = 12.04 MeV 9755 1451 194 B_v = 81.36 MeV 9755 1451 195 E_a = 385 MeV 9755 1451 196 r_v = 1.2568 fm 9755 1451 197 a_v = 0.633 fm 9755 1451 198 Surface: 9755 1451 199 W_0 = 17.2 MeV 9755 1451 200 B_s = 11.19 MeV 9755 1451 201 C_s = 0.01361 1/MeV 9755 1451 202 C_wiso = 23.5 MeV 9755 1451 203 r_s = 1.1803 fm 9755 1451 204 a_s = 0.601 fm 9755 1451 205 Spin-orbit: 9755 1451 206 V_so = 5.75 MeV 9755 1451 207 lambda_so = 0.005 1/MeV 9755 1451 208 W_so = -3.1 MeV 9755 1451 209 B_so = 160 MeV 9755 1451 210 r_so = 1.1214 fm 9755 1451 211 a_so = 0.59 fm 9755 1451 212 Coulomb: 9755 1451 213 C_coul = 1.3 9755 1451 214 r_c = 1.2452 fm 9755 1451 215 a_c = 0.545 fm 9755 1451 216 Deformation: 9755 1451 217 beta_2 = 0.213 9755 1451 218 beta_4 = 0.066 9755 1451 219 beta_6 = 0.0015 9755 1451 220 9755 1451 221 * Calculated strength function 9755 1451 222 S0= 0.96e-4 S1= 4.44e-4 R'= 8.78 fm (En=1 keV) 9755 1451 223 -------------------------------------------------- 9755 1451 224 9755 1451 225 Table 2. Level Scheme of Bk-250 9755 1451 226 ------------------- 9755 1451 227 No. Ex(MeV) J PI 9755 1451 228 ------------------- 9755 1451 229 0 0.00000 2 - * 9755 1451 230 1 0.03447 3 - * 9755 1451 231 2 0.03559 4 + 9755 1451 232 3 0.07833 5 + 9755 1451 233 4 0.08026 4 - * 9755 1451 234 5 0.08640 7 + 9755 1451 235 6 0.09749 5 - 9755 1451 236 7 0.10383 1 - 9755 1451 237 8 0.11544 3 + 9755 1451 238 9 0.12501 2 - 9755 1451 239 10 0.13049 6 + 9755 1451 240 11 0.13732 5 - * 9755 1451 241 12 0.14647 2 - 9755 1451 242 13 0.14860 4 + 9755 1451 243 14 0.15700 8 + 9755 1451 244 15 0.15739 3 - 9755 1451 245 16 0.16709 6 - 9755 1451 246 17 0.17512 1 + 9755 1451 247 18 0.17999 3 - 9755 1451 248 19 0.19100 7 + 9755 1451 249 20 0.20364 4 - 9755 1451 250 ------------------- 9755 1451 251 *) Coupled levels in CC calculation 9755 1451 252 9755 1451 253 Table 3. Level density parameters 9755 1451 254 -------------------------------------------------------- 9755 1451 255 Nuclide a* Pair Eshell T E0 Ematch 9755 1451 256 1/MeV MeV MeV MeV MeV MeV 9755 1451 257 -------------------------------------------------------- 9755 1451 258 Bk-251 19.2285 0.7574 2.4685 0.3849 -1.0085 3.1309 9755 1451 259 Bk-250 19.1626 0.0000 1.8225 0.3135 -0.9672 1.3776 9755 1451 260 Bk-249 19.0966 0.7605 1.6239 0.3821 -0.8440 2.9526 9755 1451 261 Bk-248 19.0305 0.0000 1.2435 0.2843 -0.6878 1.0000 9755 1451 262 Bk-247 18.9645 0.7635 1.3193 0.3836 -0.7996 2.9113 9755 1451 263 -------------------------------------------------------- 9755 1451 264 9755 1451 265 Table 4. Fission barrier parameters 9755 1451 266 ---------------------------------------- 9755 1451 267 Nuclide V_A hw_A V_B hw_B 9755 1451 268 MeV MeV MeV MeV 9755 1451 269 ---------------------------------------- 9755 1451 270 Bk-251 6.200 0.800 4.800 0.520 9755 1451 271 Bk-250 6.200 0.650 5.550 0.450 9755 1451 272 Bk-249 6.200 0.800 4.800 0.520 9755 1451 273 Bk-248 6.200 0.650 5.550 0.450 9755 1451 274 Bk-247 6.200 0.800 4.800 0.520 9755 1451 275 ---------------------------------------- 9755 1451 276 9755 1451 277 Table 5. Level density above inner saddle 9755 1451 278 -------------------------------------------------------- 9755 1451 279 Nuclide a* Pair Eshell T E0 Ematch 9755 1451 280 1/MeV MeV MeV MeV MeV MeV 9755 1451 281 -------------------------------------------------------- 9755 1451 282 Bk-251 21.5360 0.8837 2.6000 0.3200 -1.5275 2.8837 9755 1451 283 Bk-250 21.4621 0.0000 2.6000 0.3206 -2.4112 2.0000 9755 1451 284 Bk-249 21.3881 0.8872 2.6000 0.3212 -1.5240 2.8872 9755 1451 285 Bk-248 21.3142 0.0000 2.6000 0.3218 -2.4112 2.0000 9755 1451 286 Bk-247 21.2402 0.8908 2.6000 0.3224 -1.5204 2.8908 9755 1451 287 -------------------------------------------------------- 9755 1451 288 9755 1451 289 Table 6. Level density above outer saddle 9755 1451 290 -------------------------------------------------------- 9755 1451 291 Nuclide a* Pair Eshell T E0 Ematch 9755 1451 292 1/MeV MeV MeV MeV MeV MeV 9755 1451 293 -------------------------------------------------------- 9755 1451 294 Bk-251 21.5360 0.8837 1.0400 0.3484 -0.8269 2.8837 9755 1451 295 Bk-250 21.4621 0.0000 1.0000 0.3495 -1.7100 2.0000 9755 1451 296 Bk-249 21.3881 0.8872 0.9600 0.3506 -0.8222 2.8872 9755 1451 297 Bk-248 21.3142 0.0000 0.9200 0.3517 -1.7088 2.0000 9755 1451 298 Bk-247 21.2402 0.8908 0.8800 0.3529 -0.8175 2.8908 9755 1451 299 -------------------------------------------------------- 9755 1451 300 9755 1451 301 Table 7. Gamma-ray strength function for Bk-251 9755 1451 302 -------------------------------------------------------- 9755 1451 303 K0 = 1.500 E0 = 4.500 (MeV) 9755 1451 304 * E1: ER = 11.36 (MeV) EG = 2.70 (MeV) SIG = 255.32 (mb) 9755 1451 305 ER = 14.26 (MeV) EG = 4.16 (MeV) SIG = 510.64 (mb) 9755 1451 306 * M1: ER = 6.50 (MeV) EG = 4.00 (MeV) SIG = 1.83 (mb) 9755 1451 307 * E2: ER = 9.99 (MeV) EG = 3.10 (MeV) SIG = 7.20 (mb) 9755 1451 308 -------------------------------------------------------- 9755 1451 309 9755 1451 310 9755 1451 311 References 9755 1451 312 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9755 1451 313 2) R.J.Tuttld: INDC(NDS)-107/G+Special, p.29 (1979). 9755 1451 314 3) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9755 1451 315 4) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9755 1451 316 5) H.Diamond et al.: J. Inorg. Nucl. Chem., 30, 2553 (1968). 9755 1451 317 6) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9755 1451 318 7) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9755 1451 319 8) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9755 1451 320 Japanese. 9755 1451 321 9) C.Kalbach: Phys. Rev. C33, 818 (1986). 9755 1451 322 10) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9755 1451 323 11) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9755 1451 324 12) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9755 1451 325 13) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9755 1451 326 14) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9755 1451 327 15) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9755 1451 328 9755 1451 329 1 451 343 19755 1451 330 2 151 4 19755 1451 331 3 4 32 19755 1451 332 3 16 14 19755 1451 333 3 17 9 19755 1451 334 3 18 121 19755 1451 335 3 37 6 19755 1451 336 3 102 157 19755 1451 337 8 4 2 19755 1451 338 8 16 2 19755 1451 339 8 17 2 19755 1451 340 8 18 2 19755 1451 341 8 37 2 19755 1451 342 8 102 2 19755 1451 343 9755 1 099999 9755 0 0 0 9.725000+4 2.479300+2 0 0 1 09755 2151 1 9.725000+4 1.000000+0 0 0 1 09755 2151 2 1.000000-5 4.000000-1 0 0 0 09755 2151 3 2.000000+0 8.779000-1 0 0 0 09755 2151 4 9755 2 099999 9755 0 0 0 9.725000+4 2.479300+2 0 0 0 09755 3 4 1 0.000000+0-3.447200+4 0 0 1 869755 3 4 2 86 2 9755 3 4 3 3.461100+4 0.000000+0 3.573050+4 4.271940-2 5.000000+4 2.958371-19755 3 4 4 7.000000+4 5.248840-1 7.864190+4 6.023740-1 8.058170+4 6.188252-19755 3 4 5 8.674850+4 6.793334-1 9.788620+4 7.886297-1 1.000000+5 8.099081-19755 3 4 6 1.029490+5 8.353511-1 1.042470+5 8.465557-1 1.159080+5 1.000972+09755 3 4 7 1.200000+5 1.091205+0 1.255110+5 1.173857+0 1.310180+5 1.290563+09755 3 4 8 1.378740+5 1.400425+0 1.400000+5 1.431796+0 1.470630+5 1.530051+09755 3 4 9 1.491940+5 1.575258+0 1.576330+5 1.719590+0 1.580260+5 1.725517+09755 3 4 10 1.677630+5 1.885421+0 1.700000+5 1.918521+0 1.758290+5 2.000670+09755 3 4 11 1.807160+5 2.082070+0 1.917700+5 2.242924+0 2.000000+5 2.346098+09755 3 4 12 2.044580+5 2.385364+0 2.500000+5 2.655449+0 3.000000+5 2.780707+09755 3 4 13 4.000000+5 2.766302+0 5.000000+5 2.840328+0 6.000000+5 2.835127+09755 3 4 14 7.000000+5 2.874636+0 8.000000+5 2.884574+0 9.000000+5 2.916568+09755 3 4 15 1.000000+6 2.969839+0 1.100000+6 3.014739+0 1.200000+6 3.059097+09755 3 4 16 1.300000+6 3.096444+0 1.400000+6 3.132938+0 1.500000+6 3.154293+09755 3 4 17 1.600000+6 3.172617+0 1.700000+6 3.173932+0 1.800000+6 3.171166+09755 3 4 18 1.900000+6 3.154028+0 2.000000+6 3.132827+0 2.100000+6 3.102203+09755 3 4 19 2.300000+6 3.030613+0 2.500000+6 2.949524+0 2.700000+6 2.865379+09755 3 4 20 3.000000+6 2.735964+0 3.500000+6 2.564624+0 4.000000+6 2.406776+09755 3 4 21 4.500000+6 2.317996+0 5.000000+6 2.255427+0 5.500000+6 1.892527+09755 3 4 22 6.000000+6 1.402590+0 6.500000+6 1.061308+0 7.000000+6 8.444131-19755 3 4 23 7.500000+6 7.063275-1 8.000000+6 6.233954-1 8.500000+6 5.666317-19755 3 4 24 9.000000+6 5.280672-1 9.500000+6 4.976555-1 1.000000+7 4.733119-19755 3 4 25 1.050000+7 4.525884-1 1.100000+7 4.337800-1 1.150000+7 4.159975-19755 3 4 26 1.200000+7 3.986184-1 1.250000+7 3.823757-1 1.300000+7 3.654159-19755 3 4 27 1.350000+7 3.522780-1 1.400000+7 3.370046-1 1.450000+7 3.244579-19755 3 4 28 1.500000+7 3.124398-1 1.550000+7 3.016143-1 1.600000+7 2.907997-19755 3 4 29 1.650000+7 2.809992-1 1.700000+7 2.712870-1 1.750000+7 2.627662-19755 3 4 30 1.800000+7 2.547157-1 1.850000+7 2.464619-1 1.900000+7 2.401025-19755 3 4 31 1.950000+7 2.333648-1 2.000000+7 2.264787-1 9755 3 4 32 9755 3 099999 9.725000+4 2.479300+2 0 0 0 09755 3 16 1 -4.969570+6-4.969570+6 0 0 1 319755 3 16 2 31 2 9755 3 16 3 4.989610+6 0.000000+0 5.500000+6 3.368940-1 6.000000+6 8.069690-19755 3 16 4 6.500000+6 1.030150+0 7.000000+6 1.075310+0 7.500000+6 1.050300+09755 3 16 5 8.000000+6 1.014040+0 8.500000+6 9.691950-1 9.000000+6 9.383520-19755 3 16 6 9.500000+6 9.135730-1 1.000000+7 9.006430-1 1.050000+7 8.890180-19755 3 16 7 1.100000+7 8.776990-1 1.150000+7 8.431660-1 1.200000+7 7.732760-19755 3 16 8 1.250000+7 6.813150-1 1.300000+7 5.855700-1 1.350000+7 4.953180-19755 3 16 9 1.400000+7 4.231650-1 1.450000+7 3.647400-1 1.500000+7 3.199570-19755 3 16 10 1.550000+7 2.863790-1 1.600000+7 2.613330-1 1.650000+7 2.426830-19755 3 16 11 1.700000+7 2.281260-1 1.750000+7 2.164320-1 1.800000+7 2.062890-19755 3 16 12 1.850000+7 1.986690-1 1.900000+7 1.891550-1 1.950000+7 1.826710-19755 3 16 13 2.000000+7 1.770110-1 9755 3 16 14 9755 3 099999 9.725000+4 2.479300+2 0 0 0 09755 3 17 1 -1.127130+7-1.127130+7 0 0 1 189755 3 17 2 18 2 9755 3 17 3 1.131670+7 0.000000+0 1.200000+7 6.659980-4 1.250000+7 6.122080-39755 3 17 4 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