JENDL-5 (Neutron sublibrary (activation cs)) Cf-253 0 0 0 0 9.825300+4 2.509110+2 0 0 6 19864 1451 1 0.000000+0 1.000000+0 0 0 0 69864 1451 2 1.000000+0 2.000000+7 0 0 10 59864 1451 3 2.936000+2 0.000000+0 4 0 313 149864 1451 4 98-Cf-253 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9864 1451 5 DIST-DEC21 20100304 9864 1451 6 ----JENDL-5 MATERIAL 9864 9864 1451 7 -----INCIDENT NEUTRON DATA 9864 1451 8 ------ENDF-6 FORMAT 9864 1451 9 9864 1451 10 History 9864 1451 11 07-10 Theoretical calculation was performed with CCONE code. 9864 1451 12 07-11 Data were compiled as JENDL/AC-2008/1/. 9864 1451 13 09-02 MF=1 was revised. 9864 1451 14 10-02 Data of prompt gamma rays due to fission were given. 9864 1451 15 10-03 Covariance data were given. 9864 1451 16 9864 1451 17 21-11 revised by O.Iwamoto 9864 1451 18 (MF3/MT19-21,38) deleted 9864 1451 19 (MF8/MT16-18,37,102) JENDL/AD-2017 adopted 9864 1451 20 (MF8/MT4) added 9864 1451 21 9864 1451 22 MF=1 General information 9864 1451 23 MT=452 Number of Neutrons per fission 9864 1451 24 Sum of MT's=455 and 456. 9864 1451 25 9864 1451 26 MT=455 Delayed neutron data 9864 1451 27 Estimated from systematics by Tuttle/2/, Benedetti et al./3/ 9864 1451 28 and Waldo et al./4/ 9864 1451 29 9864 1451 30 MT=456 Number of prompt neutrons per fission 9864 1451 31 Estimated from Howerton's systematics/5/. 9864 1451 32 9864 1451 33 9864 1451 34 MF= 2 Resonance parameters 9864 1451 35 MT=151 9864 1451 36 No resonance parameters are given. 9864 1451 37 9864 1451 38 9864 1451 39 Thermal cross sections and resonance integrals (at 300K) 9864 1451 40 ------------------------------------------------------- 9864 1451 41 0.0253 eV reson. integ.(*) 9864 1451 42 (barns) (barns) 9864 1451 43 ------------------------------------------------------- 9864 1451 44 total 1331.6 9864 1451 45 elastic 10.52 9864 1451 46 fission 1300.7 965 9864 1451 47 capture 20.00 658 9864 1451 48 ------------------------------------------------------- 9864 1451 49 (*) In the energy range from 0.5 eV to 10 MeV. 9864 1451 50 9864 1451 51 9864 1451 52 MF= 3 Neutron cross sections 9864 1451 53 9864 1451 54 Below 0.6 eV: 9864 1451 55 * Elastic scattering cross section is 10.5 b calculated from 9864 1451 56 scattering radius of 9.135 fm/6/. 9864 1451 57 * Fission cross section of 1300+-240 b at 0.0253 eV was 9864 1451 58 measured by Wild et al./7/ 9864 1451 59 * Effective capture cross section of 17.6+-1.8 b was measured 9864 1451 60 by Bemis et al./8/. In the present work, capture cross 9864 1451 61 section of 20 b at 0.0253 eV was assumed. 9864 1451 62 9864 1451 63 Above 0.6 eV: 9864 1451 64 Cross sections calculated with CCONE code/6/ were adopted. 9864 1451 65 9864 1451 66 MT= 1 Total cross section 9864 1451 67 The cross section was calculated with CC OMP of Soukhovitskii 9864 1451 68 et al./9/ 9864 1451 69 9864 1451 70 9864 1451 71 MF= 4 Angular distributions of secondary neutrons 9864 1451 72 MT=2 Elastic scattering 9864 1451 73 Calculated with CCONE code/6/. 9864 1451 74 9864 1451 75 MT=18 Fission 9864 1451 76 Isotropic distributions in the laboratory system were assumed.9864 1451 77 9864 1451 78 9864 1451 79 MF= 5 Energy distributions of secondary neutrons 9864 1451 80 MT=18 Prompt netrons 9864 1451 81 Calculated with CCONE code/6/. 9864 1451 82 9864 1451 83 9864 1451 84 MF= 6 Energy-angle distributions 9864 1451 85 Calculated with CCONE code/6/. 9864 1451 86 Distributions from fission (MT=18) are not included. 9864 1451 87 9864 1451 88 9864 1451 89 MF=12 Photon production multiplicities 9864 1451 90 MT=18 Fission 9864 1451 91 Calculated from the total energy released by the prompt 9864 1451 92 gamma-rays due to fission which was estimated from its 9864 1451 93 systematics, and the average energy of gamma-rays. 9864 1451 94 9864 1451 95 9864 1451 96 MF=14 Photon angular distributions 9864 1451 97 MT=18 Fission 9864 1451 98 Isotoropic distributions were assumed. 9864 1451 99 9864 1451 100 9864 1451 101 MF=15 Continuous photon energy spectra 9864 1451 102 MT=18 Fission 9864 1451 103 Experimental data measured by Verbinski et al./10/ for 9864 1451 104 Pu-239 thermal fission were adopted. 9864 1451 105 9864 1451 106 9864 1451 107 MF=31 Covariances of average number of neutrons per fission 9864 1451 108 MT=452 Number of neutrons per fission 9864 1451 109 Sum of covariances for MT=455 and MT=456. 9864 1451 110 9864 1451 111 MT=455 9864 1451 112 Error of 15% was assumed. 9864 1451 113 9864 1451 114 MT=456 9864 1451 115 Covariance was obtained by fitting a linear function to the 9864 1451 116 at 0.0 and 5.0 MeV with an uncertainty of 10%. 9864 1451 117 9864 1451 118 9864 1451 119 MF=33 Covariances of neutron cross sections 9864 1451 120 Covariances were given to all the cross sections by using 9864 1451 121 KALMAN code/11/ and the covariances of model parameters 9864 1451 122 used in the cross-section calculations. 9864 1451 123 9864 1451 124 For the following cross sections, standard deviations in the 9864 1451 125 energy region below 0.6 eV were assumed as follows: 9864 1451 126 9864 1451 127 Total 88 % 9864 1451 128 Elastic scattering 90 % 9864 1451 129 Fission 90 % 9864 1451 130 Capture 90 % 9864 1451 131 9864 1451 132 9864 1451 133 MF=34 Covariances for Angular Distributions 9864 1451 134 MT=2 Elastic scattering 9864 1451 135 Covariances were given only to P1 components. 9864 1451 136 9864 1451 137 9864 1451 138 MF=35 Covariances for Energy Distributions 9864 1451 139 MT=18 Fission spectra 9864 1451 140 Estimated with CCONE and KALMAN codes. 9864 1451 141 9864 1451 142 9864 1451 143 ***************************************************************** 9864 1451 144 Calculation with CCONE code 9864 1451 145 ***************************************************************** 9864 1451 146 9864 1451 147 Models and parameters used in the CCONE/6/ calculation 9864 1451 148 1) Coupled channel optical model 9864 1451 149 Levels in the rotational band were included. Optical model 9864 1451 150 potential and coupled levels are shown in Table 1. 9864 1451 151 9864 1451 152 2) Two-component exciton model/12/ 9864 1451 153 * Global parametrization of Koning-Duijvestijn/13/ 9864 1451 154 was used. 9864 1451 155 * Gamma emission channel/14/ was added to simulate direct 9864 1451 156 and semi-direct capture reaction. 9864 1451 157 9864 1451 158 3) Hauser-Feshbach statistical model 9864 1451 159 * Moldauer width fluctuation correction/15/ was included. 9864 1451 160 * Neutron, gamma and fission decay channel were included. 9864 1451 161 * Transmission coefficients of neutrons were taken from 9864 1451 162 coupled channel calculation in Table 1. 9864 1451 163 * The level scheme of the target is shown in Table 2. 9864 1451 164 * Level density formula of constant temperature and Fermi-gas 9864 1451 165 model were used with shell energy correction and collective 9864 1451 166 enhancement factor. Parameters are shown in Table 3. 9864 1451 167 * Fission channel: 9864 1451 168 Double humped fission barriers were assumed. 9864 1451 169 Fission barrier penetrabilities were calculated with 9864 1451 170 Hill-Wheler formula/16/. Fission barrier parameters were 9864 1451 171 shown in Table 4. Transition state model was used and 9864 1451 172 continuum levels are assumed above the saddles. The level 9864 1451 173 density parameters for inner and outer saddles are shown in 9864 1451 174 Tables 5 and 6, respectively. 9864 1451 175 * Gamma-ray strength function of Kopecky et al/17/,/18/ 9864 1451 176 was used. The prameters are shown in Table 7. 9864 1451 177 9864 1451 178 9864 1451 179 ------------------------------------------------------------------9864 1451 180 Tables 9864 1451 181 ------------------------------------------------------------------9864 1451 182 9864 1451 183 Table 1. Coupled channel calculation 9864 1451 184 -------------------------------------------------- 9864 1451 185 * rigid rotor model was applied 9864 1451 186 * coupled levels = 0,1,2,3,6 (see Table 2) 9864 1451 187 * optical potential parameters /9/ 9864 1451 188 Volume: 9864 1451 189 V_0 = 49.97 MeV 9864 1451 190 lambda_HF = 0.01004 1/MeV 9864 1451 191 C_viso = 15.9 MeV 9864 1451 192 A_v = 12.04 MeV 9864 1451 193 B_v = 81.36 MeV 9864 1451 194 E_a = 385 MeV 9864 1451 195 r_v = 1.2568 fm 9864 1451 196 a_v = 0.633 fm 9864 1451 197 Surface: 9864 1451 198 W_0 = 17.2 MeV 9864 1451 199 B_s = 11.19 MeV 9864 1451 200 C_s = 0.01361 1/MeV 9864 1451 201 C_wiso = 23.5 MeV 9864 1451 202 r_s = 1.1803 fm 9864 1451 203 a_s = 0.601 fm 9864 1451 204 Spin-orbit: 9864 1451 205 V_so = 5.75 MeV 9864 1451 206 lambda_so = 0.005 1/MeV 9864 1451 207 W_so = -3.1 MeV 9864 1451 208 B_so = 160 MeV 9864 1451 209 r_so = 1.1214 fm 9864 1451 210 a_so = 0.59 fm 9864 1451 211 Coulomb: 9864 1451 212 C_coul = 1.3 9864 1451 213 r_c = 1.2452 fm 9864 1451 214 a_c = 0.545 fm 9864 1451 215 Deformation: 9864 1451 216 beta_2 = 0.213 9864 1451 217 beta_4 = 0.066 9864 1451 218 beta_6 = 0.0015 9864 1451 219 9864 1451 220 * Calculated strength function 9864 1451 221 S0= 1.55e-4 S1= 2.88e-4 R'= 9.13 fm (En=1 keV) 9864 1451 222 -------------------------------------------------- 9864 1451 223 9864 1451 224 Table 2. Level Scheme of Cf-253 9864 1451 225 ------------------- 9864 1451 226 No. Ex(MeV) J PI 9864 1451 227 ------------------- 9864 1451 228 0 0.00000 7/2 + * 9864 1451 229 1 0.06161 9/2 + * 9864 1451 230 2 0.13662 11/2 + * 9864 1451 231 3 0.22590 13/2 + * 9864 1451 232 4 0.24101 9/2 + 9864 1451 233 5 0.32121 11/2 + 9864 1451 234 6 0.32900 15/2 + * 9864 1451 235 ------------------- 9864 1451 236 *) Coupled levels in CC calculation 9864 1451 237 9864 1451 238 Table 3. Level density parameters 9864 1451 239 -------------------------------------------------------- 9864 1451 240 Nuclide a* Pair Eshell T E0 Ematch 9864 1451 241 1/MeV MeV MeV MeV MeV MeV 9864 1451 242 -------------------------------------------------------- 9864 1451 243 Cf-254 19.4263 1.5059 2.4305 0.3644 -0.0499 3.6204 9864 1451 244 Cf-253 19.3604 0.7544 2.0655 0.3319 -0.4196 2.3962 9864 1451 245 Cf-252 19.2945 1.5119 1.7395 0.3655 0.0444 3.5280 9864 1451 246 Cf-251 19.2285 0.7574 1.2773 0.3926 -0.9361 3.0632 9864 1451 247 Cf-250 19.1626 1.5179 1.0208 0.3974 -0.1838 3.8400 9864 1451 248 -------------------------------------------------------- 9864 1451 249 9864 1451 250 Table 4. Fission barrier parameters 9864 1451 251 ---------------------------------------- 9864 1451 252 Nuclide V_A hw_A V_B hw_B 9864 1451 253 MeV MeV MeV MeV 9864 1451 254 ---------------------------------------- 9864 1451 255 Cf-254 6.200 1.040 5.400 0.600 9864 1451 256 Cf-253 5.600 1.000 4.600 0.800 9864 1451 257 Cf-252 6.000 1.040 5.000 0.800 9864 1451 258 Cf-251 6.200 0.800 5.000 0.600 9864 1451 259 Cf-250 6.200 1.040 5.400 0.600 9864 1451 260 ---------------------------------------- 9864 1451 261 9864 1451 262 Table 5. Level density above inner saddle 9864 1451 263 -------------------------------------------------------- 9864 1451 264 Nuclide a* Pair Eshell T E0 Ematch 9864 1451 265 1/MeV MeV MeV MeV MeV MeV 9864 1451 266 -------------------------------------------------------- 9864 1451 267 Cf-254 21.7575 1.7569 2.5000 0.3191 -0.6561 3.7569 9864 1451 268 Cf-253 21.6837 0.8802 2.5000 0.3407 -1.8541 3.1802 9864 1451 269 Cf-252 21.6098 1.7638 2.5000 0.3202 -0.6492 3.7638 9864 1451 270 Cf-251 21.5360 0.8837 2.5000 0.3208 -1.5294 2.8837 9864 1451 271 Cf-250 21.4621 1.7709 2.5000 0.2827 -0.1068 3.2709 9864 1451 272 -------------------------------------------------------- 9864 1451 273 9864 1451 274 Table 6. Level density above outer saddle 9864 1451 275 -------------------------------------------------------- 9864 1451 276 Nuclide a* Pair Eshell T E0 Ematch 9864 1451 277 1/MeV MeV MeV MeV MeV MeV 9864 1451 278 -------------------------------------------------------- 9864 1451 279 Cf-254 21.7575 1.7569 1.1200 0.3455 0.0447 3.7569 9864 1451 280 Cf-253 21.6837 0.8802 1.0800 0.3466 -0.8314 2.8802 9864 1451 281 Cf-252 21.6098 1.7638 1.0400 0.3477 0.0528 3.7638 9864 1451 282 Cf-251 21.5360 0.8837 1.0000 0.3488 -0.8268 2.8837 9864 1451 283 Cf-250 21.4621 1.7709 0.9600 0.3499 0.0610 3.7709 9864 1451 284 -------------------------------------------------------- 9864 1451 285 9864 1451 286 Table 7. Gamma-ray strength function for Cf-254 9864 1451 287 -------------------------------------------------------- 9864 1451 288 K0 = 1.500 E0 = 4.500 (MeV) 9864 1451 289 * E1: ER = 11.39 (MeV) EG = 2.71 (MeV) SIG = 259.56 (mb) 9864 1451 290 ER = 14.17 (MeV) EG = 4.11 (MeV) SIG = 519.13 (mb) 9864 1451 291 * M1: ER = 6.47 (MeV) EG = 4.00 (MeV) SIG = 1.86 (mb) 9864 1451 292 * E2: ER = 9.95 (MeV) EG = 3.06 (MeV) SIG = 7.35 (mb) 9864 1451 293 -------------------------------------------------------- 9864 1451 294 9864 1451 295 9864 1451 296 References 9864 1451 297 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9864 1451 298 2) R.J.Tuttld: INDC(NDS)-107/G+Special, p.29 (1979). 9864 1451 299 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 9864 1451 300 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 9864 1451 301 5) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9864 1451 302 6) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9864 1451 303 7) J.F.Wild et al.: J. Inorg. Nucl. Chem., 35, 1063 (1973). 9864 1451 304 8) C.E.Bemis, Jr. et al.: Nucl. Sci. Eng., 41, 146 (1970). 9864 1451 305 9) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9864 1451 306 10) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9864 1451 307 11) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9864 1451 308 Japanese. 9864 1451 309 12) C.Kalbach: Phys. Rev. C33, 818 (1986). 9864 1451 310 13) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9864 1451 311 14) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9864 1451 312 15) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9864 1451 313 16) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9864 1451 314 17) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9864 1451 315 18) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9864 1451 316 9864 1451 317 1 451 331 19864 1451 318 2 151 4 19864 1451 319 3 4 27 19864 1451 320 3 16 14 19864 1451 321 3 17 10 19864 1451 322 3 18 130 19864 1451 323 3 37 6 19864 1451 324 3 102 175 19864 1451 325 8 4 2 19864 1451 326 8 16 2 19864 1451 327 8 17 2 19864 1451 328 8 18 2 19864 1451 329 8 37 2 19864 1451 330 8 102 2 19864 1451 331 9864 1 099999 9864 0 0 0 9.825300+4 2.509110+2 0 0 1 09864 2151 1 9.825300+4 1.000000+0 0 0 1 09864 2151 2 1.000000-5 6.000000-1 0 0 0 09864 2151 3 3.500000+0 9.135000-1 0 0 0 09864 2151 4 9864 2 099999 9864 0 0 0 9.825300+4 2.509110+2 0 0 0 09864 3 4 1 0.000000+0-6.161000+4 0 0 1 729864 3 4 2 72 2 9864 3 4 3 6.185550+4 0.000000+0 7.000000+4 1.683100-1 1.000000+5 3.937840-19864 3 4 4 1.108790+5 4.487724-1 1.200000+5 4.948947-1 1.371640+5 5.651532-19864 3 4 5 1.400000+5 5.865323-1 1.700000+5 7.422193-1 2.000000+5 8.715417-19864 3 4 6 2.268000+5 9.487889-1 2.419700+5 9.970386-1 2.419710+5 9.970397-19864 3 4 7 2.500000+5 1.057376+0 3.000000+5 1.268491+0 3.224900+5 1.318970+09864 3 4 8 3.303110+5 1.342991+0 4.000000+5 1.476625+0 5.000000+5 1.706103+09864 3 4 9 6.000000+5 1.919351+0 7.000000+5 2.143976+0 8.000000+5 2.322250+09864 3 4 10 9.000000+5 2.480393+0 1.000000+6 2.630047+0 1.100000+6 2.759056+09864 3 4 11 1.200000+6 2.874136+0 1.300000+6 2.969866+0 1.400000+6 3.054363+09864 3 4 12 1.500000+6 3.112565+0 1.600000+6 3.161989+0 1.700000+6 3.185410+09864 3 4 13 1.800000+6 3.202126+0 1.900000+6 3.199550+0 2.000000+6 3.192066+09864 3 4 14 2.100000+6 3.173939+0 2.300000+6 3.127227+0 2.500000+6 3.073131+09864 3 4 15 2.700000+6 3.018588+0 3.000000+6 2.942947+0 3.500000+6 2.814668+09864 3 4 16 4.000000+6 2.689786+0 4.500000+6 2.496488+0 5.000000+6 2.073844+09864 3 4 17 5.500000+6 1.414081+0 6.000000+6 9.721531-1 6.500000+6 7.155202-19864 3 4 18 7.000000+6 5.745216-1 7.500000+6 4.967653-1 8.000000+6 4.501174-19864 3 4 19 8.500000+6 4.186336-1 9.000000+6 3.949361-1 9.500000+6 3.754613-19864 3 4 20 1.000000+7 3.583773-1 1.050000+7 3.430183-1 1.100000+7 3.284041-19864 3 4 21 1.150000+7 3.142750-1 1.200000+7 3.007935-1 1.250000+7 2.879730-19864 3 4 22 1.300000+7 2.761760-1 1.350000+7 2.651761-1 1.400000+7 2.542006-19864 3 4 23 1.450000+7 2.445540-1 1.500000+7 2.354227-1 1.550000+7 2.270684-19864 3 4 24 1.600000+7 2.188652-1 1.650000+7 2.116001-1 1.700000+7 2.042755-19864 3 4 25 1.750000+7 1.979362-1 1.800000+7 1.922182-1 1.850000+7 1.861029-19864 3 4 26 1.900000+7 1.802980-1 1.950000+7 1.760145-1 2.000000+7 1.704847-19864 3 4 27 9864 3 099999 9.825300+4 2.509110+2 0 0 0 09864 3 16 1 -4.804290+6-4.804290+6 0 0 1 329864 3 16 2 32 2 9864 3 16 3 4.823440+6 0.000000+0 5.000000+6 9.738360-3 5.500000+6 1.591630-19864 3 16 4 6.000000+6 2.786780-1 6.500000+6 3.214260-1 7.000000+6 3.360830-19864 3 16 5 7.500000+6 3.368880-1 8.000000+6 3.316560-1 8.500000+6 3.257930-19864 3 16 6 9.000000+6 3.239470-1 9.500000+6 3.281440-1 1.000000+7 3.363700-19864 3 16 7 1.050000+7 3.414740-1 1.100000+7 3.329850-1 1.150000+7 3.082120-19864 3 16 8 1.200000+7 2.716440-1 1.250000+7 2.303570-1 1.300000+7 1.918030-19864 3 16 9 1.350000+7 1.586320-1 1.400000+7 1.313560-1 1.450000+7 1.120220-19864 3 16 10 1.500000+7 9.626040-2 1.550000+7 8.501770-2 1.600000+7 7.674290-29864 3 16 11 1.650000+7 7.043560-2 1.700000+7 6.568210-2 1.750000+7 6.175740-29864 3 16 12 1.800000+7 5.880910-2 1.850000+7 5.639180-2 1.900000+7 5.448840-29864 3 16 13 1.950000+7 5.241660-2 2.000000+7 4.968630-2 9864 3 16 14 9864 3 099999 9.825300+4 2.509110+2 0 0 0 09864 3 17 1 -1.097620+7-1.097620+7 0 0 1 199864 3 17 2 19 2 9864 3 17 3 1.102000+7 0.000000+0 1.150000+7 2.429740-4 1.200000+7 6.168080-39864 3 17 4 1.250000+7 2.615670-2 1.300000+7 5.556850-2 1.350000+7 9.026600-29864 3 17 5 1.400000+7 1.252100-1 1.450000+7 1.563430-1 1.500000+7 1.811650-19864 3 17 6 1.550000+7 1.918790-1 1.600000+7 1.984790-1 1.650000+7 2.076860-19864 3 17 7 1.700000+7 2.091760-1 1.750000+7 2.093370-1 1.800000+7 2.038810-19864 3 17 8 1.850000+7 1.986570-1 1.900000+7 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