JENDL-5 (Neutron sublibrary (activation cs)) Cf-246 0 0 0 0 9.824600+4 2.439550+2 0 0 6 19843 1451 1 0.000000+0 1.000000+0 0 0 0 69843 1451 2 1.000000+0 2.000000+7 0 0 10 59843 1451 3 2.936000+2 0.000000+0 4 0 299 129843 1451 4 98-Cf-246 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9843 1451 5 DIST-DEC21 20100304 9843 1451 6 ----JENDL-5 MATERIAL 9843 9843 1451 7 -----INCIDENT NEUTRON DATA 9843 1451 8 ------ENDF-6 FORMAT 9843 1451 9 9843 1451 10 History 9843 1451 11 07-10 Theoretical calculation was performed with CCONE code. 9843 1451 12 07-11 Data were compiled as JENDL/AC-2008/1/. 9843 1451 13 10-02 Data of prompt gamma rays due to fission were given. 9843 1451 14 10-03 Covariance data were given. 9843 1451 15 21-11 revised by O.Iwamoto 9843 1451 16 (MF3/MT19-21,38) deleted 9843 1451 17 (MF8/MT4,16-18,102) added 9843 1451 18 9843 1451 19 9843 1451 20 MF=1 General information 9843 1451 21 MT=452 Number of Neutrons per fission 9843 1451 22 Sum of MT's=455 and 456. 9843 1451 23 9843 1451 24 MT=455 Delayed neutron data 9843 1451 25 Estimated from systematics by Tuttle/2/, Benedetti et al./3/ 9843 1451 26 and Waldo et al./4/ 9843 1451 27 9843 1451 28 MT=456 Number of prompt neutrons per fission 9843 1451 29 Estimated from Howerton's systematics/5/. 9843 1451 30 9843 1451 31 9843 1451 32 MF= 2 Resonance parameters 9843 1451 33 MT=151 9843 1451 34 No resonance parameters are given. 9843 1451 35 9843 1451 36 9843 1451 37 Thermal cross sections and resonance integrals (at 300K) 9843 1451 38 ------------------------------------------------------- 9843 1451 39 0.0253 eV reson. integ.(*) 9843 1451 40 (barns) (barns) 9843 1451 41 ------------------------------------------------------- 9843 1451 42 total 3112.5 9843 1451 43 elastic 10.62 9843 1451 44 fission 1400.6 604 9843 1451 45 capture 1700.8 722 9843 1451 46 ------------------------------------------------------- 9843 1451 47 (*) In the energy range from 0.5 eV to 10 MeV. 9843 1451 48 9843 1451 49 9843 1451 50 MF= 3 Neutron cross sections 9843 1451 51 Below 4.0 eV: 9843 1451 52 * Elastic scattering cross section is 10.6 b calculated from 9843 1451 53 scattering radius of 9.164 fm/6/. 9843 1451 54 * Fission and capture cross sections calculated with CCONE 9843 1451 55 code/6/ were exptrapolated. 9843 1451 56 9843 1451 57 Above 4.0 eV: 9843 1451 58 Cross sections calculated with CCONE code/6/ were adopted. 9843 1451 59 9843 1451 60 MT= 1 Total cross section 9843 1451 61 The cross section was calculated with CC OMP of Soukhovitskii 9843 1451 62 et al./7/ 9843 1451 63 9843 1451 64 9843 1451 65 MF= 4 Angular distributions of secondary neutrons 9843 1451 66 MT=2 Elastic scattering 9843 1451 67 Calculated with CCONE code/6/. 9843 1451 68 9843 1451 69 MT=18 Fission 9843 1451 70 Isotropic distributions in the laboratory system were assumed.9843 1451 71 9843 1451 72 9843 1451 73 MF= 5 Energy distributions of secondary neutrons 9843 1451 74 MT=18 Prompt neutrons 9843 1451 75 Calculated with CCONE code/6/. 9843 1451 76 9843 1451 77 9843 1451 78 MF= 6 Energy-angle distributions 9843 1451 79 Calculated with CCONE code/6/. 9843 1451 80 Distributions from fission (MT=18) are not included. 9843 1451 81 9843 1451 82 9843 1451 83 MF=12 Photon production multiplicities 9843 1451 84 MT=18 Fission 9843 1451 85 Calculated from the total energy released by the prompt 9843 1451 86 gamma-rays due to fission which was estimated from its 9843 1451 87 systematics, and the average energy of gamma-rays. 9843 1451 88 9843 1451 89 9843 1451 90 MF=14 Photon angular distributions 9843 1451 91 MT=18 Fission 9843 1451 92 Isotoropic distributions were assumed. 9843 1451 93 9843 1451 94 9843 1451 95 MF=15 Continuous photon energy spectra 9843 1451 96 MT=18 Fission 9843 1451 97 Experimental data measured by Verbinski et al./8/ for 9843 1451 98 Pu-239 thermal fission were adopted. 9843 1451 99 9843 1451 100 9843 1451 101 MF=31 Covariances of average number of neutrons per fission 9843 1451 102 MT=452 Number of neutrons per fission 9843 1451 103 Sum of covariances for MT=455 and MT=456. 9843 1451 104 9843 1451 105 MT=455 9843 1451 106 Error of 15% was assumed. 9843 1451 107 9843 1451 108 MT=456 9843 1451 109 Covariance was obtained by fitting a linear function to the 9843 1451 110 at 0.0 and 5.0 MeV with an uncertainty of 10%. 9843 1451 111 9843 1451 112 9843 1451 113 MF=33 Covariances of neutron cross sections 9843 1451 114 Covariances were given to all the cross sections by using 9843 1451 115 KALMAN code/9/ and the covariances of model parameters 9843 1451 116 used in the cross-section calculations. 9843 1451 117 9843 1451 118 For the following cross sections, standard deviations in the 9843 1451 119 energy region below 4.0 eV were assumed as follows: 9843 1451 120 9843 1451 121 Total 64 % 9843 1451 122 Elastic scattering 90 % 9843 1451 123 Fission 90 % 9843 1451 124 Capture 90 % 9843 1451 125 9843 1451 126 9843 1451 127 MF=34 Covariances for Angular Distributions 9843 1451 128 MT=2 Elastic scattering 9843 1451 129 Covariances were given only to P1 components. 9843 1451 130 9843 1451 131 9843 1451 132 MF=35 Covariances for Energy Distributions 9843 1451 133 MT=18 Fission spectra 9843 1451 134 Estimated with CCONE and KALMAN codes. 9843 1451 135 9843 1451 136 9843 1451 137 ***************************************************************** 9843 1451 138 Calculation with CCONE code 9843 1451 139 ***************************************************************** 9843 1451 140 9843 1451 141 Models and parameters used in the CCONE/6/ calculation 9843 1451 142 1) Coupled channel optical model 9843 1451 143 Levels in the rotational band were included. Optical model 9843 1451 144 potential and coupled levels are shown in Table 1. 9843 1451 145 9843 1451 146 2) Two-component exciton model/10/ 9843 1451 147 * Global parametrization of Koning-Duijvestijn/11/ 9843 1451 148 was used. 9843 1451 149 * Gamma emission channel/12/ was added to simulate direct 9843 1451 150 and semi-direct capture reaction. 9843 1451 151 9843 1451 152 3) Hauser-Feshbach statistical model 9843 1451 153 * Moldauer width fluctuation correction/13/ was included. 9843 1451 154 * Neutron, gamma and fission decay channel were included. 9843 1451 155 * Transmission coefficients of neutrons were taken from 9843 1451 156 coupled channel calculation in Table 1. 9843 1451 157 * The level scheme of the target is shown in Table 2. 9843 1451 158 * Level density formula of constant temperature and Fermi-gas 9843 1451 159 model were used with shell energy correction and collective 9843 1451 160 enhancement factor. Parameters are shown in Table 3. 9843 1451 161 * Fission channel: 9843 1451 162 Double humped fission barriers were assumed. 9843 1451 163 Fission barrier penetrabilities were calculated with 9843 1451 164 Hill-Wheler formula/14/. Fission barrier parameters were 9843 1451 165 shown in Table 4. Transition state model was used and 9843 1451 166 continuum levels are assumed above the saddles. The level 9843 1451 167 density parameters for inner and outer saddles are shown in 9843 1451 168 Tables 5 and 6, respectively. 9843 1451 169 * Gamma-ray strength function of Kopecky et al/15/,/16/ 9843 1451 170 was used. The prameters are shown in Table 7. 9843 1451 171 9843 1451 172 9843 1451 173 ------------------------------------------------------------------9843 1451 174 Tables 9843 1451 175 ------------------------------------------------------------------9843 1451 176 9843 1451 177 Table 1. Coupled channel calculation 9843 1451 178 -------------------------------------------------- 9843 1451 179 * rigid rotor model was applied 9843 1451 180 * coupled levels = 0,1,2,3,4 (see Table 2) 9843 1451 181 * optical potential parameters /7/ 9843 1451 182 Volume: 9843 1451 183 V_0 = 49.97 MeV 9843 1451 184 lambda_HF = 0.01004 1/MeV 9843 1451 185 C_viso = 15.9 MeV 9843 1451 186 A_v = 12.04 MeV 9843 1451 187 B_v = 81.36 MeV 9843 1451 188 E_a = 385 MeV 9843 1451 189 r_v = 1.2568 fm 9843 1451 190 a_v = 0.633 fm 9843 1451 191 Surface: 9843 1451 192 W_0 = 17.2 MeV 9843 1451 193 B_s = 11.19 MeV 9843 1451 194 C_s = 0.01361 1/MeV 9843 1451 195 C_wiso = 23.5 MeV 9843 1451 196 r_s = 1.1803 fm 9843 1451 197 a_s = 0.601 fm 9843 1451 198 Spin-orbit: 9843 1451 199 V_so = 5.75 MeV 9843 1451 200 lambda_so = 0.005 1/MeV 9843 1451 201 W_so = -3.1 MeV 9843 1451 202 B_so = 160 MeV 9843 1451 203 r_so = 1.1214 fm 9843 1451 204 a_so = 0.59 fm 9843 1451 205 Coulomb: 9843 1451 206 C_coul = 1.3 9843 1451 207 r_c = 1.2452 fm 9843 1451 208 a_c = 0.545 fm 9843 1451 209 Deformation: 9843 1451 210 beta_2 = 0.213 9843 1451 211 beta_4 = 0.066 9843 1451 212 beta_6 = 0.0015 9843 1451 213 9843 1451 214 * Calculated strength function 9843 1451 215 S0= 1.24e-4 S1= 3.10e-4 R'= 9.16 fm (En=1 keV) 9843 1451 216 -------------------------------------------------- 9843 1451 217 9843 1451 218 Table 2. Level Scheme of Cf-246 9843 1451 219 ------------------- 9843 1451 220 No. Ex(MeV) J PI 9843 1451 221 ------------------- 9843 1451 222 0 0.00000 0 + * 9843 1451 223 1 0.04400 2 + * 9843 1451 224 2 0.14700 4 + * 9843 1451 225 3 0.30800 6 + * 9843 1451 226 4 0.52800 8 + * 9843 1451 227 ------------------- 9843 1451 228 *) Coupled levels in CC calculation 9843 1451 229 9843 1451 230 Table 3. Level density parameters 9843 1451 231 -------------------------------------------------------- 9843 1451 232 Nuclide a* Pair Eshell T E0 Ematch 9843 1451 233 1/MeV MeV MeV MeV MeV MeV 9843 1451 234 -------------------------------------------------------- 9843 1451 235 Cf-247 18.9645 0.7635 0.5924 0.3748 -0.6176 2.6898 9843 1451 236 Cf-246 18.8984 1.5302 0.7686 0.4030 -0.1574 3.8448 9843 1451 237 Cf-245 18.8322 0.7667 0.7561 0.3907 -0.7780 2.9023 9843 1451 238 Cf-244 18.7661 1.5364 0.8187 0.4109 -0.2255 3.9461 9843 1451 239 -------------------------------------------------------- 9843 1451 240 9843 1451 241 Table 4. Fission barrier parameters 9843 1451 242 ---------------------------------------- 9843 1451 243 Nuclide V_A hw_A V_B hw_B 9843 1451 244 MeV MeV MeV MeV 9843 1451 245 ---------------------------------------- 9843 1451 246 Cf-247 6.700 1.000 5.900 0.800 9843 1451 247 Cf-246 6.200 1.040 5.400 0.600 9843 1451 248 Cf-245 6.700 1.000 5.900 0.800 9843 1451 249 Cf-244 6.200 1.040 5.400 0.600 9843 1451 250 ---------------------------------------- 9843 1451 251 9843 1451 252 Table 5. Level density above inner saddle 9843 1451 253 -------------------------------------------------------- 9843 1451 254 Nuclide a* Pair Eshell T E0 Ematch 9843 1451 255 1/MeV MeV MeV MeV MeV MeV 9843 1451 256 -------------------------------------------------------- 9843 1451 257 Cf-247 21.2402 0.8908 2.5000 0.3232 -1.5224 2.8908 9843 1451 258 Cf-246 21.1662 1.7852 2.5000 0.3238 -0.6280 3.7852 9843 1451 259 Cf-245 21.0921 0.8944 2.5000 0.3244 -1.5188 2.8944 9843 1451 260 Cf-244 21.0180 1.7925 2.5000 0.3251 -0.6208 3.7925 9843 1451 261 -------------------------------------------------------- 9843 1451 262 9843 1451 263 Table 6. Level density above outer saddle 9843 1451 264 -------------------------------------------------------- 9843 1451 265 Nuclide a* Pair Eshell T E0 Ematch 9843 1451 266 1/MeV MeV MeV MeV MeV MeV 9843 1451 267 -------------------------------------------------------- 9843 1451 268 Cf-247 21.2402 0.8908 0.8400 0.3533 -0.8173 2.8908 9843 1451 269 Cf-246 21.1662 1.7852 0.8000 0.3544 0.0777 3.7852 9843 1451 270 Cf-245 21.0921 0.8944 0.7600 0.3556 -0.8125 2.8944 9843 1451 271 Cf-244 21.0180 1.7925 0.7200 0.3567 0.0862 3.7925 9843 1451 272 -------------------------------------------------------- 9843 1451 273 9843 1451 274 Table 7. Gamma-ray strength function for Cf-247 9843 1451 275 -------------------------------------------------------- 9843 1451 276 K0 = 1.500 E0 = 4.500 (MeV) 9843 1451 277 * E1: ER = 11.41 (MeV) EG = 2.72 (MeV) SIG = 251.84 (mb) 9843 1451 278 ER = 14.31 (MeV) EG = 4.19 (MeV) SIG = 503.67 (mb) 9843 1451 279 * M1: ER = 6.53 (MeV) EG = 4.00 (MeV) SIG = 1.79 (mb) 9843 1451 280 * E2: ER = 10.04 (MeV) EG = 3.15 (MeV) SIG = 7.36 (mb) 9843 1451 281 -------------------------------------------------------- 9843 1451 282 9843 1451 283 9843 1451 284 References 9843 1451 285 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9843 1451 286 2) R.J.Tuttld: INDC(NDS)-107/G+Special, p.29 (1979). 9843 1451 287 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 9843 1451 288 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 9843 1451 289 5) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9843 1451 290 6) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9843 1451 291 7) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9843 1451 292 8) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9843 1451 293 9) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9843 1451 294 Japanese. 9843 1451 295 10) C.Kalbach: Phys. Rev. C33, 818 (1986). 9843 1451 296 11) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9843 1451 297 12) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9843 1451 298 13) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9843 1451 299 14) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9843 1451 300 15) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9843 1451 301 16) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9843 1451 302 9843 1451 303 1 451 315 19843 1451 304 2 151 4 19843 1451 305 3 4 27 19843 1451 306 3 16 12 19843 1451 307 3 17 8 19843 1451 308 3 18 121 19843 1451 309 3 102 147 19843 1451 310 8 4 2 19843 1451 311 8 16 2 19843 1451 312 8 17 2 19843 1451 313 8 18 2 19843 1451 314 8 102 2 19843 1451 315 9843 1 099999 9843 0 0 0 9.824600+4 2.439550+2 0 0 1 09843 2151 1 9.824600+4 1.000000+0 0 0 1 09843 2151 2 1.000000-5 4.000000+0 0 0 0 09843 2151 3 0.000000+0 9.164000-1 0 0 0 09843 2151 4 9843 2 099999 9843 0 0 0 9.824600+4 2.439550+2 0 0 0 09843 3 4 1 0.000000+0-4.400000+4 0 0 1 719843 3 4 2 71 2 9843 3 4 3 4.418040+4 0.000000+0 5.000000+4 4.793910-2 7.000000+4 2.614080-19843 3 4 4 1.000000+5 5.198640-1 1.109040+5 5.835177-1 1.200000+5 6.366245-19843 3 4 5 1.400000+5 7.344263-1 1.476030+5 7.673304-1 1.700000+5 8.534556-19843 3 4 6 2.000000+5 9.646978-1 2.500000+5 1.069891+0 3.000000+5 1.152177+09843 3 4 7 3.092620+5 1.156040+0 3.092630+5 1.156041+0 4.000000+5 1.180113+09843 3 4 8 5.000000+5 1.207924+0 5.301640+5 1.195386+0 6.000000+5 1.158941+09843 3 4 9 7.000000+5 1.136128+0 8.000000+5 1.128635+0 9.000000+5 1.142648+09843 3 4 10 1.000000+6 1.171878+0 1.100000+6 1.202617+0 1.200000+6 1.232185+09843 3 4 11 1.300000+6 1.256401+0 1.400000+6 1.277686+0 1.500000+6 1.289774+09843 3 4 12 1.600000+6 1.299006+0 1.700000+6 1.298837+0 1.800000+6 1.296471+09843 3 4 13 1.900000+6 1.286108+0 2.000000+6 1.274392+0 2.100000+6 1.257150+09843 3 4 14 2.300000+6 1.218105+0 2.500000+6 1.174252+0 2.700000+6 1.129748+09843 3 4 15 3.000000+6 1.068945+0 3.500000+6 9.961468-1 4.000000+6 9.643571-19843 3 4 16 4.500000+6 9.661027-1 5.000000+6 9.835624-1 5.500000+6 9.840273-19843 3 4 17 6.000000+6 9.176201-1 6.500000+6 8.132285-1 7.000000+6 7.191494-19843 3 4 18 7.500000+6 6.467670-1 8.000000+6 5.924149-1 8.500000+6 5.508521-19843 3 4 19 9.000000+6 5.181316-1 9.500000+6 4.914588-1 1.000000+7 4.689655-19843 3 4 20 1.050000+7 4.493932-1 1.100000+7 4.317718-1 1.150000+7 4.156045-19843 3 4 21 1.200000+7 4.004197-1 1.250000+7 3.859773-1 1.300000+7 3.722423-19843 3 4 22 1.350000+7 3.591481-1 1.400000+7 3.466771-1 1.450000+7 3.348351-19843 3 4 23 1.500000+7 3.236562-1 1.550000+7 3.133293-1 1.600000+7 3.031115-19843 3 4 24 1.650000+7 2.939893-1 1.700000+7 2.849864-1 1.750000+7 2.769123-19843 3 4 25 1.800000+7 2.689805-1 1.850000+7 2.618789-1 1.900000+7 2.548911-19843 3 4 26 1.950000+7 2.486123-1 2.000000+7 2.424424-1 9843 3 4 27 9843 3 099999 9.824600+4 2.439550+2 0 0 0 09843 3 16 1 -7.366460+6-7.366460+6 0 0 1 279843 3 16 2 27 2 9843 3 16 3 7.396650+6 0.000000+0 7.500000+6 1.540000-5 8.000000+6 6.219820-39843 3 16 4 8.500000+6 2.301950-2 9.000000+6 4.115180-2 9.500000+6 5.505820-29843 3 16 5 1.000000+7 6.377120-2 1.050000+7 6.729350-2 1.100000+7 7.286350-29843 3 16 6 1.150000+7 7.695620-2 1.200000+7 8.092690-2 1.250000+7 8.766070-29843 3 16 7 1.300000+7 9.383870-2 1.350000+7 1.004330-1 1.400000+7 1.061990-19843 3 16 8 1.450000+7 1.090150-1 1.500000+7 1.078500-1 1.550000+7 1.021720-19843 3 16 9 1.600000+7 9.574650-2 1.650000+7 8.745260-2 1.700000+7 7.941480-29843 3 16 10 1.750000+7 7.357650-2 1.800000+7 6.753130-2 1.850000+7 6.254740-29843 3 16 11 1.900000+7 5.848560-2 1.950000+7 5.524900-2 2.000000+7 5.260400-29843 3 16 12 9843 3 099999 9.824600+4 2.439550+2 0 0 0 09843 3 17 1 -1.353020+7-1.353020+7 0 0 1 149843 3 17 2 14 2 9843 3 17 3 1.358560+7 0.000000+0 1.400000+7 9.136230-6 1.450000+7 4.254160-49843 3 17 4 1.500000+7 1.827670-3 1.550000+7 3.978500-3 1.600000+7 6.054400-39843 3 17 5 1.650000+7 8.714300-3 1.700000+7 1.136420-2 1.750000+7 1.276280-29843 3 17 6 1.800000+7 1.375550-2 1.850000+7 1.450800-2 1.900000+7 1.516700-29843 3 17 7 1.950000+7 1.578750-2 2.000000+7 1.651460-2 9843 3 17 8 9843 3 099999 9.824600+4 2.439550+2 0 0 0 09843 3 18 1 2.089000+8 2.089000+8 0 0 1 3529843 3 18 2 352 2 9843 3 18 3 1.000000-5 7.047510+4 1.103037-5 6.710274+4 1.216691-5 6.389175+49843 3 18 4 1.342055-5 6.083441+4 1.480336-5 5.792336+4 1.632865-5 5.515160+49843 3 18 5 1.801111-5 5.251247+4 1.986691-5 4.999962+4 2.191394-5 4.760701+49843 3 18 6 2.417189-5 4.532889+4 2.666248-5 4.315977+4 2.940971-5 4.109444+49843 3 18 7 3.243999-5 3.912794+4 3.578251-5 3.725553+4 3.946943-5 3.547272+49843 3 18 8 4.353624-5 3.377521+4 4.802208-5 3.215892+4 5.297013-5 3.061997+49843 3 18 9 5.842801-5 2.915466+4 6.444825-5 2.775946+4 7.108881-5 2.643102+49843 3 18 10 7.841358-5 2.516614+4 8.649308-5 2.396178+4 9.540506-5 2.281505+49843 3 18 11 1.052353-4 2.172319+4 1.160784-4 2.068358+4 1.280388-4 1.969371+49843 3 18 12 1.412315-4 1.875120+4 1.557836-4 1.785379+4 1.718351-4 1.699932+49843 3 18 13 1.895404-4 1.618574+4 2.090701-4 1.541109+4 2.306120-4 1.467351+49843 3 18 14 2.543736-4 1.397123+4 2.805835-4 1.330255+4 3.094939-4 1.266587+49843 3 18 15 3.413832-4 1.205966+4 3.765583-4 1.148246+4 4.153577-4 1.093288+49843 3 18 16 4.581549-4 1.040960+4 5.053618-4 9.911368+3 5.574328-4 9.436979+39843 3 18 17 6.148689-4 8.985295+3 6.782232-4 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