JENDL-5 (Neutron sublibrary (activation cs)) Es-254M 0 0 0 0 9.925400+4 2.519050+2 0 0 6 19915 1451 1 8.420000+4 1.000000+0 1 1 0 69915 1451 2 1.000000+0 2.000000+7 0 0 10 59915 1451 3 2.936000+2 0.000000+0 4 0 316 149915 1451 4 99-Es-254MJAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9915 1451 5 DIST-DEC21 20100304 9915 1451 6 ----JENDL-5 MATERIAL 9915 9915 1451 7 -----INCIDENT NEUTRON DATA 9915 1451 8 ------ENDF-6 FORMAT 9915 1451 9 9915 1451 10 History 9915 1451 11 07-11 Theoretical calculation was performed with CCONE code. 9915 1451 12 07-12 Data were compiled as JENDL/AC-2008/1/. 9915 1451 13 10-02 Data of prompt gamma rays due to fission were given. 9915 1451 14 10-03 Covariance data were given. 9915 1451 15 21-11 revised by O.Iwamoto 9915 1451 16 (MF3/MT19-21,38) deleted 9915 1451 17 (MF8/MT4,16-18,37,102) added 9915 1451 18 9915 1451 19 9915 1451 20 MF=1 General information 9915 1451 21 MT=452 Number of Neutrons per fission 9915 1451 22 Sum of MT's=455 and 456. 9915 1451 23 9915 1451 24 MT=455 Delayed neutron data 9915 1451 25 (same as JENDL-3.3 Es-254) 9915 1451 26 Estimated from systematics by Tuttle/2/, Benedetti et al./3/ 9915 1451 27 and Waldo et al./4/ 9915 1451 28 Decay constants were calculated by Brady and England /5/. 9915 1451 29 9915 1451 30 MT=456 Number of prompt neutrons per fission 9915 1451 31 (same as JENDL-3.3 Es-254) 9915 1451 32 Estimated from Howerton's systematics/6/. 9915 1451 33 9915 1451 34 9915 1451 35 MF= 2 Resonance parameters 9915 1451 36 MT=151 9915 1451 37 No resonance parameters were given. 9915 1451 38 9915 1451 39 Thermal cross sections and resonance integrals (at 300K) 9915 1451 40 ------------------------------------------------------- 9915 1451 41 0.0253 eV reson. integ.(*) 9915 1451 42 (barns) (barns) 9915 1451 43 ------------------------------------------------------- 9915 1451 44 total 2260.5 9915 1451 45 elastic 9.419 9915 1451 46 fission 2000.7 1430 9915 1451 47 capture 250.1 178 9915 1451 48 ------------------------------------------------------- 9915 1451 49 (*) In the energy range from 0.5 eV to 10 MeV. 9915 1451 50 9915 1451 51 9915 1451 52 MF= 3 Neutron cross sections 9915 1451 53 Below 0.3 eV: 9915 1451 54 The fission cross section at 0.0253 eV was assumed to be 2000 9915 1451 55 b which is almost the same as Es-254 fission cross section. 9915 1451 56 The capture cross section at 0.0253 eV was assumed to be 250 9915 1451 57 b from the fission cross section at 0.0253 eV and capture to 9915 1451 58 fission ratio at 1 eV calculated with CCONE code/7/. 9915 1451 59 The elastic scattering cross section of 9.4 b was calculated 9915 1451 60 from scattering radius of 8.628 fm/7/. 9915 1451 61 9915 1451 62 Above 0.3 eV: 9915 1451 63 Cross sections calculated with CCONE code/7/ were adopted. 9915 1451 64 The same parameters as those for Es-254 were used in the 9915 1451 65 CCONE calculation. 9915 1451 66 9915 1451 67 9915 1451 68 MF= 4 Angular distributions of secondary neutrons 9915 1451 69 MT=2 Elastic scattering 9915 1451 70 Calculated with CCONE code/7/. 9915 1451 71 9915 1451 72 MT=18 Fission 9915 1451 73 Isotropic distributions in the laboratory system were assumed.9915 1451 74 9915 1451 75 9915 1451 76 MF= 5 Energy distributions of secondary neutrons 9915 1451 77 MT=18 Prompt netrons 9915 1451 78 Calculated with CCONE code/7/. 9915 1451 79 9915 1451 80 MT=455 Delayed neutrons 9915 1451 81 Calculated by Brady and England /5/ for Es-154. 9915 1451 82 9915 1451 83 9915 1451 84 MF= 6 Energy-angle distributions 9915 1451 85 Calculated with CCONE code/7/. 9915 1451 86 Distributions from fission (MT=18) are not included. 9915 1451 87 9915 1451 88 9915 1451 89 MF=12 Photon production multiplicities 9915 1451 90 MT=18 Fission 9915 1451 91 Calculated from the total energy released by the prompt 9915 1451 92 gamma-rays due to fission which was estimated from its 9915 1451 93 systematics, and the average energy of gamma-rays. 9915 1451 94 9915 1451 95 9915 1451 96 MF=14 Photon angular distributions 9915 1451 97 MT=18 Fission 9915 1451 98 Isotoropic distributions were assumed. 9915 1451 99 9915 1451 100 9915 1451 101 MF=15 Continuous photon energy spectra 9915 1451 102 MT=18 Fission 9915 1451 103 Experimental data measured by Verbinski et al./8/ for 9915 1451 104 Pu-239 thermal fission were adopted. 9915 1451 105 9915 1451 106 9915 1451 107 MF=31 Covariances of average number of neutrons per fission 9915 1451 108 MT=452 Number of neutrons per fission 9915 1451 109 Sum of covariances for MT=455 and MT=456. 9915 1451 110 9915 1451 111 MT=455 9915 1451 112 Error of 15% was assumed. 9915 1451 113 9915 1451 114 MT=456 9915 1451 115 Covariance was obtained by fitting a linear function to the 9915 1451 116 at 0.0 and 5.0 MeV with an uncertainty of 10%. 9915 1451 117 9915 1451 118 9915 1451 119 MF=33 Covariances of neutron cross sections 9915 1451 120 Covariances were given to all the cross sections by using 9915 1451 121 KALMAN code/9/ and the covariances of model parameters 9915 1451 122 used in the cross-section calculations. 9915 1451 123 9915 1451 124 Covariances of the fission cross section were determined from 9915 1451 125 experimental data. 9915 1451 126 9915 1451 127 For the following cross sections, standard deviations in the 9915 1451 128 energy region below 0.3 eV were assumed as follows: 9915 1451 129 9915 1451 130 Total 80 % 9915 1451 131 Elastic scattering 90 % 9915 1451 132 Fission 90 % 9915 1451 133 Capture 90 % 9915 1451 134 9915 1451 135 9915 1451 136 MF=34 Covariances for Angular Distributions 9915 1451 137 MT=2 Elastic scattering 9915 1451 138 Covariances were given only to P1 components. 9915 1451 139 9915 1451 140 9915 1451 141 MF=35 Covariances for Energy Distributions 9915 1451 142 MT=18 Fission spectra 9915 1451 143 Estimated with CCONE and KALMAN codes. 9915 1451 144 9915 1451 145 9915 1451 146 ***************************************************************** 9915 1451 147 Calculation with CCONE code 9915 1451 148 ***************************************************************** 9915 1451 149 9915 1451 150 Models and parameters used in the CCONE/7/ calculation 9915 1451 151 1) Coupled channel optical model 9915 1451 152 Levels in the rotational band were included. Optical model 9915 1451 153 potential and coupled levels are shown in Table 1. 9915 1451 154 9915 1451 155 2) Two-component exciton model/10/ 9915 1451 156 * Global parametrization of Koning-Duijvestijn/11/ 9915 1451 157 was used. 9915 1451 158 * Gamma emission channel/12/ was added to simulate direct 9915 1451 159 and semi-direct capture reaction. 9915 1451 160 9915 1451 161 3) Hauser-Feshbach statistical model 9915 1451 162 * Moldauer width fluctuation correction/13/ was included. 9915 1451 163 * Neutron, gamma and fission decay channel were included. 9915 1451 164 * Transmission coefficients of neutrons were taken from 9915 1451 165 coupled channel calculation in Table 1. 9915 1451 166 * The level scheme of the target is shown in Table 2. 9915 1451 167 * Level density formula of constant temperature and Fermi-gas 9915 1451 168 model were used with shell energy correction and collective 9915 1451 169 enhancement factor. Parameters are shown in Table 3. 9915 1451 170 * Fission channel: 9915 1451 171 Double humped fission barriers were assumed. 9915 1451 172 Fission barrier penetrabilities were calculated with 9915 1451 173 Hill-Wheler formula/14/. Fission barrier parameters were 9915 1451 174 shown in Table 4. Transition state model was used and 9915 1451 175 continuum levels are assumed above the saddles. The level 9915 1451 176 density parameters for inner and outer saddles are shown in 9915 1451 177 Tables 5 and 6, respectively. 9915 1451 178 * Gamma-ray strength function of Kopecky et al/15/,/16/ 9915 1451 179 was used. The prameters are shown in Table 7. 9915 1451 180 9915 1451 181 9915 1451 182 ------------------------------------------------------------------9915 1451 183 Tables 9915 1451 184 ------------------------------------------------------------------9915 1451 185 9915 1451 186 Table 1. Coupled channel calculation 9915 1451 187 -------------------------------------------------- 9915 1451 188 * rigid rotor model was applied 9915 1451 189 * coupled levels = 2,3,4,6 (see Table 2) 9915 1451 190 * optical potential parameters /17/ 9915 1451 191 Volume: 9915 1451 192 V_0 = 49.97 MeV 9915 1451 193 lambda_HF = 0.01004 1/MeV 9915 1451 194 C_viso = 15.9 MeV 9915 1451 195 A_v = 12.04 MeV 9915 1451 196 B_v = 81.36 MeV 9915 1451 197 E_a = 385 MeV 9915 1451 198 r_v = 1.2568 fm 9915 1451 199 a_v = 0.633 fm 9915 1451 200 Surface: 9915 1451 201 W_0 = 17.2 MeV 9915 1451 202 B_s = 11.19 MeV 9915 1451 203 C_s = 0.01361 1/MeV 9915 1451 204 C_wiso = 23.5 MeV 9915 1451 205 r_s = 1.1803 fm 9915 1451 206 a_s = 0.601 fm 9915 1451 207 Spin-orbit: 9915 1451 208 V_so = 5.75 MeV 9915 1451 209 lambda_so = 0.005 1/MeV 9915 1451 210 W_so = -3.1 MeV 9915 1451 211 B_so = 160 MeV 9915 1451 212 r_so = 1.1214 fm 9915 1451 213 a_so = 0.59 fm 9915 1451 214 Coulomb: 9915 1451 215 C_coul = 1.3 9915 1451 216 r_c = 1.2452 fm 9915 1451 217 a_c = 0.545 fm 9915 1451 218 Deformation: 9915 1451 219 beta_2 = 0.213 9915 1451 220 beta_4 = 0.066 9915 1451 221 beta_6 = 0.0015 9915 1451 222 9915 1451 223 * Calculated strength function 9915 1451 224 S0= 1.35e-4 S1= 4.60e-4 R'= 8.63 fm (En=1 keV) 9915 1451 225 -------------------------------------------------- 9915 1451 226 9915 1451 227 Table 2. Level Scheme of Es-254 9915 1451 228 ------------------- 9915 1451 229 No. Ex(MeV) J PI 9915 1451 230 ------------------- 9915 1451 231 0 0.00000 7 + 9915 1451 232 1 0.08010 8 + 9915 1451 233 2 0.08420 2 + * 9915 1451 234 3 0.11420 3 + * 9915 1451 235 4 0.15420 4 + * 9915 1451 236 5 0.17110 9 + 9915 1451 237 6 0.20420 5 + * 9915 1451 238 7 0.21470 5 - 9915 1451 239 ------------------- 9915 1451 240 *) Coupled levels in CC calculation 9915 1451 241 9915 1451 242 Table 3. Level density parameters 9915 1451 243 -------------------------------------------------------- 9915 1451 244 Nuclide a* Pair Eshell T E0 Ematch 9915 1451 245 1/MeV MeV MeV MeV MeV MeV 9915 1451 246 -------------------------------------------------------- 9915 1451 247 Es-255 19.4922 0.7515 2.2159 0.3615 -0.7550 2.8069 9915 1451 248 Es-254 19.4263 0.0000 1.6001 0.2773 -0.6899 1.0000 9915 1451 249 Es-253 19.3604 0.7544 1.3654 0.3757 -0.7841 2.8632 9915 1451 250 Es-252 19.2945 0.0000 0.8872 0.2854 -0.6910 1.0000 9915 1451 251 Es-251 19.2285 0.7574 0.6125 0.4218 -1.1719 3.3703 9915 1451 252 -------------------------------------------------------- 9915 1451 253 9915 1451 254 Table 4. Fission barrier parameters 9915 1451 255 ---------------------------------------- 9915 1451 256 Nuclide V_A hw_A V_B hw_B 9915 1451 257 MeV MeV MeV MeV 9915 1451 258 ---------------------------------------- 9915 1451 259 Es-255 6.120 0.800 4.800 0.520 9915 1451 260 Es-254 6.200 0.650 5.800 0.450 9915 1451 261 Es-253 6.200 0.800 5.400 0.520 9915 1451 262 Es-252 6.200 0.650 5.800 0.450 9915 1451 263 Es-251 6.200 0.800 5.400 0.520 9915 1451 264 ---------------------------------------- 9915 1451 265 9915 1451 266 Table 5. Level density above inner saddle 9915 1451 267 -------------------------------------------------------- 9915 1451 268 Nuclide a* Pair Eshell T E0 Ematch 9915 1451 269 1/MeV MeV MeV MeV MeV MeV 9915 1451 270 -------------------------------------------------------- 9915 1451 271 Es-255 21.8312 0.8767 2.4000 0.3193 -1.5382 2.8767 9915 1451 272 Es-254 21.7575 0.0000 2.4000 0.3199 -2.4149 2.0000 9915 1451 273 Es-253 21.6837 0.8802 2.4000 0.3205 -1.5348 2.8802 9915 1451 274 Es-252 21.6098 0.0000 2.4000 0.3211 -2.4150 2.0000 9915 1451 275 Es-251 21.5360 0.8837 2.4000 0.3217 -1.5314 2.8837 9915 1451 276 -------------------------------------------------------- 9915 1451 277 9915 1451 278 Table 6. Level density above outer saddle 9915 1451 279 -------------------------------------------------------- 9915 1451 280 Nuclide a* Pair Eshell T E0 Ematch 9915 1451 281 1/MeV MeV MeV MeV MeV MeV 9915 1451 282 -------------------------------------------------------- 9915 1451 283 Es-255 21.8312 0.8767 1.1200 0.3449 -0.8359 2.8767 9915 1451 284 Es-254 21.7575 0.0000 1.0800 0.3459 -1.7120 2.0000 9915 1451 285 Es-253 21.6837 0.8802 1.0400 0.3470 -0.8313 2.8802 9915 1451 286 Es-252 21.6098 0.0000 1.0000 0.3481 -1.7109 2.0000 9915 1451 287 Es-251 21.5360 0.8837 0.9600 0.3492 -0.8267 2.8837 9915 1451 288 -------------------------------------------------------- 9915 1451 289 9915 1451 290 Table 7. Gamma-ray strength function for Es-255 9915 1451 291 -------------------------------------------------------- 9915 1451 292 K0 = 1.500 E0 = 4.500 (MeV) 9915 1451 293 * E1: ER = 11.38 (MeV) EG = 2.71 (MeV) SIG = 261.63 (mb) 9915 1451 294 ER = 14.16 (MeV) EG = 4.11 (MeV) SIG = 523.27 (mb) 9915 1451 295 * M1: ER = 6.47 (MeV) EG = 4.00 (MeV) SIG = 1.87 (mb) 9915 1451 296 * E2: ER = 9.93 (MeV) EG = 3.05 (MeV) SIG = 7.50 (mb) 9915 1451 297 -------------------------------------------------------- 9915 1451 298 9915 1451 299 9915 1451 300 References 9915 1451 301 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9915 1451 302 2) R.J.Tuttld: INDC(NDS)-107/G+Special, p.29 (1979). 9915 1451 303 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 9915 1451 304 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 9915 1451 305 5) M.C.Brady, T.R.England: Nucl. Sci. Eng., 103, 129 (1989). 9915 1451 306 6) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9915 1451 307 7) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9915 1451 308 8) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9915 1451 309 9) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9915 1451 310 Japanese. 9915 1451 311 10) C.Kalbach: Phys. Rev. C33, 818 (1986). 9915 1451 312 11) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9915 1451 313 12) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9915 1451 314 13) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9915 1451 315 14) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9915 1451 316 15) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9915 1451 317 16) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9915 1451 318 17) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9915 1451 319 9915 1451 320 1 451 334 19915 1451 321 2 151 4 19915 1451 322 3 4 140 19915 1451 323 3 16 14 19915 1451 324 3 17 9 19915 1451 325 3 18 121 19915 1451 326 3 37 6 19915 1451 327 3 102 154 19915 1451 328 8 4 2 19915 1451 329 8 16 2 19915 1451 330 8 17 2 19915 1451 331 8 18 2 19915 1451 332 8 37 2 19915 1451 333 8 102 2 19915 1451 334 9915 1 099999 9915 0 0 0 9.925400+4 2.519050+2 0 0 1 09915 2151 1 9.925400+4 1.000000+0 0 0 1 09915 2151 2 1.000000-5 3.000000-1 0 0 0 09915 2151 3 0.000000+0 8.628000-1 0 0 0 09915 2151 4 9915 2 099999 9915 0 0 0 9.925400+4 2.519050+2 0 0 0 09915 3 4 1 8.420000+4 8.420000+4 0 0 1 4109915 3 4 2 410 2 9915 3 4 3 1.000000-5 1.502780-2 1.103037-5 1.430877-2 1.216691-5 1.362416-29915 3 4 4 1.342055-5 1.297231-2 1.480336-5 1.235165-2 1.632865-5 1.176070-29915 3 4 5 1.801111-5 1.119803-2 1.986691-5 1.066228-2 2.191394-5 1.015218-29915 3 4 6 2.417189-5 9.666484-3 2.666248-5 9.204038-3 2.940971-5 8.763723-39915 3 4 7 3.243999-5 8.344483-3 3.578251-5 7.945307-3 3.946943-5 7.565237-39915 3 4 8 4.353624-5 7.203358-3 4.802208-5 6.858799-3 5.297013-5 6.530732-39915 3 4 9 5.842801-5 6.218368-3 6.444825-5 5.920954-3 7.108881-5 5.637775-39915 3 4 10 7.841358-5 5.368151-3 8.649308-5 5.111432-3 9.540506-5 4.867000-39915 3 4 11 1.052353-4 4.634268-3 1.160784-4 4.412674-3 1.280388-4 4.201686-39915 3 4 12 1.412315-4 4.000795-3 1.557836-4 3.809519-3 1.718351-4 3.627396-39915 3 4 13 1.895404-4 3.453987-3 2.090701-4 3.288876-3 2.306120-4 3.131665-39915 3 4 14 2.543736-4 2.981974-3 2.805835-4 2.839445-3 3.094939-4 2.703733-39915 3 4 15 3.413832-4 2.574511-3 3.765583-4 2.451470-3 4.153577-4 2.334312-39915 3 4 16 4.581549-4 2.222756-3 5.053618-4 2.116534-3 5.574328-4 2.015390-39915 3 4 17 6.148689-4 1.919081-3 6.782232-4 1.827376-3 7.481052-4 1.740054-39915 3 4 18 8.251877-4 1.656906-3 9.102125-4 1.577732-3 1.003998-3 1.502342-39915 3 4 19 1.107447-3 1.430555-3 1.221555-3 1.362199-3 1.347420-3 1.297109-39915 3 4 20 1.486254-3 1.235130-3 1.639393-3 1.176113-3 1.808311-3 1.119917-39915 3 4 21 1.994634-3 1.066406-3 2.200155-3 1.015454-3 2.426853-3 9.669400-49915 3 4 22 2.676908-3 9.207480-4 2.952729-3 8.767710-4 3.256969-3 8.349070-49915 3 4 23 3.592557-3 7.950550-4 3.962723-3 7.571170-4 4.371030-3 7.209910-49915 3 4 24 4.821407-3 6.865820-4 5.318191-3 6.538010-4 5.866161-3 6.225740-49915 3 4 25 6.470592-3 5.928360-4 7.137302-3 5.645140-4 7.872708-3 5.375440-49915 3 4 26 8.683888-3 5.118610-4 9.578649-3 4.874060-4 1.056560-2 4.641120-49915 3 4 27 1.165425-2 4.419290-4 1.285507-2 4.208160-4 1.417962-2 4.007190-49915 3 4 28 1.564064-2 3.815700-4 1.725221-2 3.633320-4 1.902982-2 3.459700-49915 3 4 29 2.099059-2 3.294330-4 2.315340-2 3.136950-4 2.524188-2 3.004580-49915 3 4 30 2.530000-2 3.001130-4 2.790683-2 2.857480-4 3.078227-2 2.720620-49915 3 4 31 3.395398-2 2.590660-4 3.771669-2 2.458010-4 4.160290-2 2.340170-49915 3 4 32 4.588954-2 2.228330-4 5.061786-2 2.121720-4 5.583337-2 2.020040-49915 3 4 33 6.158627-2 1.923180-4 6.793193-2 1.831420-4 7.545630-2 1.737680-49915 3 4 34 8.323108-2 1.654290-4 9.180696-2 1.575310-4 1.012665-1 1.499930-49915 3 4 35 1.117007-1 1.428040-4 1.232100-1 1.359540-4 1.359051-1 1.294710-49915 3 4 36 1.509658-1 1.228390-4 1.665209-1 1.169390-4 1.849653-1 1.109730-49915 3 4 37 2.040236-1 1.056630-4 2.266331-1 1.002450-4 2.499846-1 9.543600-59915 3 4 38 2.738108-1 9.121070-5 3.041539-1 8.653050-5 3.354930-1 8.237650-59915 3 4 39 3.752821-1 7.789890-5 4.139500-1 7.417500-5 4.566022-1 7.062010-59915 3 4 40 5.036491-1 6.722940-5 5.516521-1 6.425940-5 6.127850-1 6.095770-59915 3 4 41 6.759245-1 5.802950-5 7.560884-1 5.487680-5 8.339934-1 5.223870-59915 3 4 42 9.329041-1 4.939640-5 1.021820+0 4.721160-5 1.119265+0 4.513160-59915 3 4 43 1.225942+0 4.314250-5 1.342854+0 4.124370-5 1.502114+0 3.902300-59915 3 4 44 1.656888+0 3.717210-5 1.853393+0 3.517180-5 2.044360+0 3.351770-59915 3 4 45 2.255005+0 3.192090-5 2.469931+0 3.051030-5 2.762862+0 2.886090-59915 3 4 46 3.069036+0 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