JENDL-5 (Neutron sublibrary (activation cs)) U -231 0 0 0 0 9.223100+4 2.290520+2 0 0 6 19216 1451 1 0.000000+0 1.000000+0 0 0 0 69216 1451 2 1.000000+0 2.000000+7 0 0 10 59216 1451 3 2.936000+2 0.000000+0 4 0 319 129216 1451 4 92-U -231 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9216 1451 5 DIST-DEC21 20100304 9216 1451 6 ----JENDL-5 MATERIAL 9216 9216 1451 7 -----INCIDENT NEUTRON DATA 9216 1451 8 ------ENDF-6 FORMAT 9216 1451 9 9216 1451 10 History 9216 1451 11 07-10 Theoretical calculation was performed with CCONE code. 9216 1451 12 07-11 Data were compiled as JENDL/AC-2008/1/. 9216 1451 13 10-02 Data of prompt gamma rays due to fission were given. 9216 1451 14 10-03 Covariance data were given. 9216 1451 15 21-11 revised by O.Iwamoto 9216 1451 16 (MF3/MT19-21,38) deleted 9216 1451 17 (MF8/MT4,16-18,102) added 9216 1451 18 9216 1451 19 9216 1451 20 MF=1 General information 9216 1451 21 MT=452 Number of Neutrons per fission 9216 1451 22 Sum of MT's=455 and 456. 9216 1451 23 9216 1451 24 MT=455 Delayed neutron data 9216 1451 25 Estimated from systematics by Tuttle/2/, Benedetti et al./3/ 9216 1451 26 and Waldo et al./4/ 9216 1451 27 9216 1451 28 MT=456 Number of prompt neutrons per fission 9216 1451 29 Estimated from Howerton's systematics/5/. 9216 1451 30 9216 1451 31 9216 1451 32 MF= 2 Resonance parameters 9216 1451 33 MT=151 9216 1451 34 No resonance parameters are given. 9216 1451 35 9216 1451 36 9216 1451 37 Thermal cross sections and resonance integrals (at 300K) 9216 1451 38 ------------------------------------------------------- 9216 1451 39 0.0253 eV reson. integ.(*) 9216 1451 40 (barns) (barns) 9216 1451 41 ------------------------------------------------------- 9216 1451 42 total 282.1 9216 1451 43 elastic 11.73 9216 1451 44 fission 250.1 1050 9216 1451 45 capture 20.01 161 9216 1451 46 ------------------------------------------------------- 9216 1451 47 (*) In the energy range from 0.5 eV to 10 MeV. 9216 1451 48 9216 1451 49 9216 1451 50 MF= 3 Neutron cross sections 9216 1451 51 Below 0.15 eV: 9216 1451 52 * Elastic scattering cross section is 11.7 b calculated from 9216 1451 53 scattering radius of 9.664 fm/6/. 9216 1451 54 * Fission cross section is in the 1/v shape. 9216 1451 55 Experimental data of 200 to 300 b at 0.0253 eV measured by 9216 1451 56 Bentley et al. /7/ was adopted as 250 b. 9216 1451 57 * Capture cross section is in the 1/v shape. 9216 1451 58 Cross section of 20 b at 0.0253 eV was estimated from 9216 1451 59 systematics. 9216 1451 60 9216 1451 61 Above 0.15 eV: 9216 1451 62 Cross sections calculated with CCONE code/6/ were adopted. 9216 1451 63 9216 1451 64 MT= 1 Total cross section 9216 1451 65 The cross section was calculated with CC OMP of Soukhovitskii 9216 1451 66 et al./8/. 9216 1451 67 9216 1451 68 MT=18 Fission cross section 9216 1451 69 The simulated (n,f) cross sections of Britt and Wilhelmy/9/ 9216 1451 70 were used to determine the parameters in the CCONE 9216 1451 71 calculation. 9216 1451 72 9216 1451 73 9216 1451 74 MF= 4 Angular distributions of secondary neutrons 9216 1451 75 MT=2 Elastic scattering 9216 1451 76 Calculated with CCONE code. 9216 1451 77 9216 1451 78 MT=18 Fission 9216 1451 79 Isotropic distributions in the laboratory system were assumed.9216 1451 80 9216 1451 81 9216 1451 82 MF= 5 Energy distributions of secondary neutrons 9216 1451 83 MT=18 Prompt neutrons 9216 1451 84 Calculated with CCONE code/6/. 9216 1451 85 9216 1451 86 9216 1451 87 MF= 6 Energy-angle distributions 9216 1451 88 Calculated with CCONE code. 9216 1451 89 Distributions from fission (MT=18) are not included. 9216 1451 90 9216 1451 91 9216 1451 92 MF=12 Photon production multiplicities 9216 1451 93 MT=18 Fission 9216 1451 94 Calculated from the total energy released by the prompt 9216 1451 95 gamma-rays due to fission which was estimated from its 9216 1451 96 systematics, and the average energy of gamma-rays. 9216 1451 97 9216 1451 98 9216 1451 99 MF=14 Photon angular distributions 9216 1451 100 MT=18 Fission 9216 1451 101 Isotoropic distributions were assumed. 9216 1451 102 9216 1451 103 9216 1451 104 MF=15 Continuous photon energy spectra 9216 1451 105 MT=18 Fission 9216 1451 106 Experimental data measured by Verbinski et al./10/ for 9216 1451 107 U-235 thermal fission were adopted. 9216 1451 108 9216 1451 109 9216 1451 110 MF=31 Covariances of average number of neutrons per fission 9216 1451 111 MT=452 Number of neutrons per fission 9216 1451 112 Sum of covariances for MT=455 and MT=456. 9216 1451 113 9216 1451 114 MT=455 9216 1451 115 Error of 15% was assumed. 9216 1451 116 9216 1451 117 MT=456 9216 1451 118 Covariance was obtained by fitting a linear function to the 9216 1451 119 at 0.0 and 5.0 MeV with an uncertainty of 5%. 9216 1451 120 9216 1451 121 9216 1451 122 MF=33 Covariances of neutron cross sections 9216 1451 123 Covariances were given to all the cross sections by using 9216 1451 124 KALMAN code/11/ and the covariances of model parameters 9216 1451 125 used in the cross-section calculations. 9216 1451 126 9216 1451 127 Covariances of the fission cross section were determined from 9216 1451 128 experimental data. 9216 1451 129 9216 1451 130 For the following cross sections, standard deviations in the 9216 1451 131 energy region below 0.15 eV were assumed as follows: 9216 1451 132 9216 1451 133 Total 80 % 9216 1451 134 Elastic scattering 90 % 9216 1451 135 Fission 90 % 9216 1451 136 Capture 90 % 9216 1451 137 9216 1451 138 9216 1451 139 MF=34 Covariances for Angular Distributions 9216 1451 140 MT=2 Elastic scattering 9216 1451 141 Covariances were given only to P1 components. 9216 1451 142 9216 1451 143 9216 1451 144 MF=35 Covariances for Energy Distributions 9216 1451 145 MT=18 Fission spectra 9216 1451 146 Estimated with CCONE and KALMAN codes. 9216 1451 147 9216 1451 148 9216 1451 149 ***************************************************************** 9216 1451 150 Calculation with CCONE code 9216 1451 151 ***************************************************************** 9216 1451 152 9216 1451 153 Models and parameters used in the CCONE/6/ calculation 9216 1451 154 1) Coupled channel optical model 9216 1451 155 Levels in the rotational band were included. Optical model 9216 1451 156 potential and coupled levels are shown in Table 1. 9216 1451 157 9216 1451 158 2) Two-component exciton model/12/ 9216 1451 159 * Global parametrization of Koning-Duijvestijn/13/ 9216 1451 160 was used. 9216 1451 161 * Gamma emission channel/14/ was added to simulate direct 9216 1451 162 and semi-direct capture reaction. 9216 1451 163 9216 1451 164 3) Hauser-Feshbach statistical model 9216 1451 165 * Moldauer width fluctuation correction/15/ was included. 9216 1451 166 * Neutron, gamma and fission decay channel were included. 9216 1451 167 * Transmission coefficients of neutrons were taken from 9216 1451 168 coupled channel calculation in Table 1. 9216 1451 169 * The level scheme of the target is shown in Table 2. 9216 1451 170 * Level density formula of constant temperature and Fermi-gas 9216 1451 171 model were used with shell energy correction and collective 9216 1451 172 enhancement factor. Parameters are shown in Table 3. 9216 1451 173 * Fission channel: 9216 1451 174 Double humped fission barriers were assumed. 9216 1451 175 Fission barrier penetrabilities were calculated with 9216 1451 176 Hill-Wheler formula/16/. Fission barrier parameters were 9216 1451 177 shown in Table 4. Transition state model was used and 9216 1451 178 continuum levels are assumed above the saddles. The level 9216 1451 179 density parameters for inner and outer saddles are shown in 9216 1451 180 Tables 5 and 6, respectively. 9216 1451 181 * Gamma-ray strength function of Kopecky et al/17/,/18/ 9216 1451 182 was used. The prameters are shown in Table 7. 9216 1451 183 9216 1451 184 9216 1451 185 ------------------------------------------------------------------9216 1451 186 Tables 9216 1451 187 ------------------------------------------------------------------9216 1451 188 9216 1451 189 Table 1. Coupled channel calculation 9216 1451 190 -------------------------------------------------- 9216 1451 191 * rigid rotor model was applied 9216 1451 192 * coupled levels = 0,2,3,5 (see Table 2) 9216 1451 193 * optical potential parameters /8/ 9216 1451 194 Volume: 9216 1451 195 V_0 = 49.97 MeV 9216 1451 196 lambda_HF = 0.01004 1/MeV 9216 1451 197 C_viso = 15.9 MeV 9216 1451 198 A_v = 12.04 MeV 9216 1451 199 B_v = 81.36 MeV 9216 1451 200 E_a = 385 MeV 9216 1451 201 r_v = 1.2568 fm 9216 1451 202 a_v = 0.633 fm 9216 1451 203 Surface: 9216 1451 204 W_0 = 17.2 MeV 9216 1451 205 B_s = 11.19 MeV 9216 1451 206 C_s = 0.01361 1/MeV 9216 1451 207 C_wiso = 23.5 MeV 9216 1451 208 r_s = 1.1803 fm 9216 1451 209 a_s = 0.601 fm 9216 1451 210 Spin-orbit: 9216 1451 211 V_so = 5.75 MeV 9216 1451 212 lambda_so = 0.005 1/MeV 9216 1451 213 W_so = -3.1 MeV 9216 1451 214 B_so = 160 MeV 9216 1451 215 r_so = 1.1214 fm 9216 1451 216 a_so = 0.59 fm 9216 1451 217 Coulomb: 9216 1451 218 C_coul = 1.3 9216 1451 219 r_c = 1.2452 fm 9216 1451 220 a_c = 0.545 fm 9216 1451 221 Deformation: 9216 1451 222 beta_2 = 0.213 9216 1451 223 beta_4 = 0.066 9216 1451 224 beta_6 = 0.0015 9216 1451 225 9216 1451 226 * Calculated strength function 9216 1451 227 S0= 1.02e-4 S1= 2.26e-4 R'= 9.66 fm (En=1 keV) 9216 1451 228 -------------------------------------------------- 9216 1451 229 9216 1451 230 Table 2. Level Scheme of U-231 9216 1451 231 ------------------- 9216 1451 232 No. Ex(MeV) J PI 9216 1451 233 ------------------- 9216 1451 234 0 0.00000 5/2 - * 9216 1451 235 1 0.04000 5/2 + 9216 1451 236 2 0.04510 7/2 - * 9216 1451 237 3 0.10309 9/2 - * 9216 1451 238 4 0.14309 9/2 + 9216 1451 239 5 0.17396 11/2 - * 9216 1451 240 6 0.21396 11/2 + 9216 1451 241 ------------------- 9216 1451 242 *) Coupled levels in CC calculation 9216 1451 243 9216 1451 244 Table 3. Level density parameters 9216 1451 245 -------------------------------------------------------- 9216 1451 246 Nuclide a* Pair Eshell T E0 Ematch 9216 1451 247 1/MeV MeV MeV MeV MeV MeV 9216 1451 248 -------------------------------------------------------- 9216 1451 249 U-232 18.3293 1.5757 2.6095 0.3887 -0.1141 3.8805 9216 1451 250 U-231 18.2614 0.7895 2.6793 0.3780 -0.7805 2.9483 9216 1451 251 U-230 18.1935 1.5825 2.6739 0.3937 -0.1508 3.9419 9216 1451 252 U-229 18.1256 0.7930 2.8715 0.3807 -0.8108 2.9930 9216 1451 253 U-228 18.0576 1.5894 2.8045 0.3969 -0.1770 3.9894 9216 1451 254 -------------------------------------------------------- 9216 1451 255 9216 1451 256 Table 4. Fission barrier parameters 9216 1451 257 ---------------------------------------- 9216 1451 258 Nuclide V_A hw_A V_B hw_B 9216 1451 259 MeV MeV MeV MeV 9216 1451 260 ---------------------------------------- 9216 1451 261 U-232 5.800 1.040 5.930 0.600 9216 1451 262 U-231 6.000 0.800 5.600 0.520 9216 1451 263 U-230 5.800 1.040 5.100 0.600 9216 1451 264 U-229 6.000 0.800 5.600 0.520 9216 1451 265 U-228 5.800 1.040 5.100 0.600 9216 1451 266 ---------------------------------------- 9216 1451 267 9216 1451 268 Table 5. Level density above inner saddle 9216 1451 269 -------------------------------------------------------- 9216 1451 270 Nuclide a* Pair Eshell T E0 Ematch 9216 1451 271 1/MeV MeV MeV MeV MeV MeV 9216 1451 272 -------------------------------------------------------- 9216 1451 273 U-232 23.3609 1.8383 2.6000 0.3384 -1.0121 4.3383 9216 1451 274 U-231 20.0518 0.9211 2.6000 0.3325 -1.4903 2.9211 9216 1451 275 U-230 19.9772 1.8463 2.6000 0.3332 -0.5651 3.8463 9216 1451 276 U-229 19.9026 0.9251 2.6000 0.3339 -1.4862 2.9251 9216 1451 277 U-228 19.8280 1.8543 2.6000 0.3346 -0.5570 3.8543 9216 1451 278 -------------------------------------------------------- 9216 1451 279 9216 1451 280 Table 6. Level density above outer saddle 9216 1451 281 -------------------------------------------------------- 9216 1451 282 Nuclide a* Pair Eshell T E0 Ematch 9216 1451 283 1/MeV MeV MeV MeV MeV MeV 9216 1451 284 -------------------------------------------------------- 9216 1451 285 U-232 23.3609 1.8383 -0.0200 0.3766 -0.2481 4.3383 9216 1451 286 U-231 20.0518 0.9211 -0.0600 0.3758 -0.7765 2.9211 9216 1451 287 U-230 19.9772 1.8463 -0.1000 0.3771 0.1493 3.8463 9216 1451 288 U-229 19.9026 0.9251 -0.1400 0.3784 -0.7712 2.9251 9216 1451 289 U-228 19.8280 1.8543 -0.1800 0.3798 0.1586 3.8543 9216 1451 290 -------------------------------------------------------- 9216 1451 291 9216 1451 292 Table 7. Gamma-ray strength function for U-232 9216 1451 293 -------------------------------------------------------- 9216 1451 294 K0 = 1.502 E0 = 4.500 (MeV) 9216 1451 295 * E1: ER = 10.90 (MeV) EG = 2.50 (MeV) SIG = 300.00 (mb) 9216 1451 296 ER = 13.80 (MeV) EG = 4.70 (MeV) SIG = 450.00 (mb) 9216 1451 297 * M1: ER = 6.67 (MeV) EG = 4.00 (MeV) SIG = 2.70 (mb) 9216 1451 298 * E2: ER = 10.25 (MeV) EG = 3.33 (MeV) SIG = 6.53 (mb) 9216 1451 299 -------------------------------------------------------- 9216 1451 300 9216 1451 301 9216 1451 302 References 9216 1451 303 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9216 1451 304 2) R.J.Tuttle: INDC(NDS)-107/G+Special, p.29 (1979). 9216 1451 305 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 9216 1451 306 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 9216 1451 307 5) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9216 1451 308 6) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9216 1451 309 7) W.Bentley et al.: CC-3699, p.6 (1946). 9216 1451 310 8) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9216 1451 311 9) H.C.Britt, J.B.Wilhelmy: Nucl. Sci. Eng., 72, 222 (1979) 9216 1451 312 10) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9216 1451 313 11) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9216 1451 314 Japanese. 9216 1451 315 12) C.Kalbach: Phys. Rev. C33, 818 (1986). 9216 1451 316 13) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9216 1451 317 14) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9216 1451 318 15) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9216 1451 319 16) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9216 1451 320 17) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9216 1451 321 18) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9216 1451 322 9216 1451 323 1 451 335 19216 1451 324 2 151 4 19216 1451 325 3 4 27 19216 1451 326 3 16 13 19216 1451 327 3 17 8 19216 1451 328 3 18 128 19216 1451 329 3 102 157 19216 1451 330 8 4 2 19216 1451 331 8 16 2 19216 1451 332 8 17 2 19216 1451 333 8 18 2 19216 1451 334 8 102 2 19216 1451 335 9216 1 099999 9216 0 0 0 9.223100+4 2.290520+2 0 0 1 09216 2151 1 9.223100+4 1.000000+0 0 0 1 09216 2151 2 1.000000-5 1.500000-1 0 0 0 09216 2151 3 2.500000+0 9.664000-1 0 0 0 09216 2151 4 9216 2 099999 9216 0 0 0 9.223100+4 2.290520+2 0 0 0 09216 3 4 1 0.000000+0-4.000000+4 0 0 1 729216 3 4 2 72 2 9216 3 4 3 4.017460+4 0.000000+0 4.529690+4 1.090930-2 5.000000+4 2.600512-29216 3 4 4 7.000000+4 6.059450-2 1.000000+5 1.045007-1 1.026610+5 1.075944-19216 3 4 5 1.035400+5 1.086165-1 1.200000+5 1.299407-1 1.400000+5 1.577394-19216 3 4 6 1.437150+5 1.628223-1 1.700000+5 2.052111-1 1.747190+5 2.123856-19216 3 4 7 1.747200+5 2.123872-1 2.000000+5 2.523164-1 2.148940+5 2.675809-19216 3 4 8 2.500000+5 3.030855-1 3.000000+5 3.509537-1 4.000000+5 4.143149-19216 3 4 9 5.000000+5 5.179954-1 6.000000+5 6.017067-1 7.000000+5 6.951089-19216 3 4 10 8.000000+5 7.716280-1 9.000000+5 8.464728-1 1.000000+6 9.228486-19216 3 4 11 1.100000+6 9.884444-1 1.200000+6 1.048461+0 1.300000+6 1.103725+09216 3 4 12 1.400000+6 1.154341+0 1.500000+6 1.199547+0 1.600000+6 1.240418+09216 3 4 13 1.700000+6 1.274817+0 1.800000+6 1.305623+0 1.900000+6 1.329743+09216 3 4 14 2.000000+6 1.350936+0 2.300000+6 1.387296+0 2.500000+6 1.396793+09216 3 4 15 2.700000+6 1.417352+0 3.000000+6 1.427099+0 3.500000+6 1.437967+09216 3 4 16 4.000000+6 1.453716+0 4.500000+6 1.466841+0 5.000000+6 1.474468+09216 3 4 17 5.500000+6 1.472248+0 6.000000+6 1.375903+0 6.500000+6 1.181260+09216 3 4 18 7.000000+6 1.005875+0 7.500000+6 8.763814-1 8.000000+6 7.831051-19216 3 4 19 8.500000+6 7.146887-1 9.000000+6 6.626045-1 9.500000+6 6.211811-19216 3 4 20 1.000000+7 5.867608-1 1.050000+7 5.570253-1 1.100000+7 5.303453-19216 3 4 21 1.150000+7 5.058595-1 1.200000+7 4.831019-1 1.250000+7 4.616102-19216 3 4 22 1.300000+7 4.411929-1 1.350000+7 4.217096-1 1.400000+7 4.032839-19216 3 4 23 1.450000+7 3.858192-1 1.500000+7 3.691396-1 1.550000+7 3.537292-19216 3 4 24 1.600000+7 3.388118-1 1.650000+7 3.253479-1 1.700000+7 3.125152-19216 3 4 25 1.750000+7 3.008991-1 1.800000+7 2.898804-1 1.850000+7 2.799479-19216 3 4 26 1.900000+7 2.705494-1 1.950000+7 2.621050-1 2.000000+7 2.541529-19216 3 4 27 9216 3 099999 9.223100+4 2.290520+2 0 0 0 09216 3 16 1 -5.878660+6-5.878660+6 0 0 1 299216 3 16 2 29 2 9216 3 16 3 5.904320+6 0.000000+0 6.500000+6 2.273040-2 7.000000+6 6.934350-29216 3 16 4 7.500000+6 1.077480-1 8.000000+6 1.357160-1 8.500000+6 1.547060-19216 3 16 5 9.000000+6 1.665060-1 9.500000+6 1.740240-1 1.000000+7 1.808730-19216 3 16 6 1.050000+7 1.892860-1 1.100000+7 2.024770-1 1.150000+7 2.170660-19216 3 16 7 1.200000+7 2.242120-1 1.250000+7 2.211090-1 1.300000+7 2.092210-19216 3 16 8 1.350000+7 1.928670-1 1.400000+7 1.753020-1 1.450000+7 1.571730-19216 3 16 9 1.500000+7 1.426780-1 1.550000+7 1.292150-1 1.600000+7 1.193240-19216 3 16 10 1.650000+7 1.101020-1 1.700000+7 1.025440-1 1.750000+7 9.643740-29216 3 16 11 1.800000+7 9.143850-2 1.850000+7 8.737670-2 1.900000+7 8.400210-29216 3 16 12 1.950000+7 8.114260-2 2.000000+7 7.855490-2 9216 3 16 13 9216 3 099999 9.223100+4 2.290520+2 0 0 0 09216 3 17 1 -1.354580+7-1.354580+7 0 0 1 149216 3 17 2 14 2 9216 3 17 3 1.360500+7 0.000000+0 1.400000+7 2.821260-7 1.450000+7 6.551020-59216 3 17 4 1.500000+7 4.259510-4 1.550000+7 1.332490-3 1.600000+7 2.335730-39216 3 17 5 1.650000+7 4.306170-3 1.700000+7 6.006280-3 1.750000+7 8.762670-39216 3 17 6 1.800000+7 1.113960-2 1.850000+7 1.399360-2 1.900000+7 1.742170-29216 3 17 7 1.950000+7 2.151080-2 2.000000+7 2.573390-2 9216 3 17 8 9216 3 099999 9.223100+4 2.290520+2 0 0 0 09216 3 18 1 1.881000+8 1.881000+8 0 0 1 3749216 3 18 2 374 2 9216 3 18 3 1.000000-5 1.259201+4 1.103037-5 1.198945+4 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