JENDL-5 (Neutron sublibrary (activation cs)) Th-233 0 0 0 0 9.023300+4 2.310400+2 0 0 6 19043 1451 1 0.000000+0 1.000000+0 0 0 0 69043 1451 2 1.000000+0 2.000000+7 0 0 10 59043 1451 3 2.936000+2 0.000000+0 4 0 325 149043 1451 4 90-Th-233 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9043 1451 5 DIST-DEC21 20100303 9043 1451 6 ----JENDL-5 MATERIAL 9043 9043 1451 7 -----INCIDENT NEUTRON DATA 9043 1451 8 ------ENDF-6 FORMAT 9043 1451 9 9043 1451 10 History 9043 1451 11 07-06 Theoretical calculation was performed with CCONE code. 9043 1451 12 07-07 Data were compiled as JENDL/AC-2008/1/. 9043 1451 13 10-02 Data of prompt gamma rays due to fission were given. 9043 1451 14 10-03 Covariance data were given. 9043 1451 15 21-11 revised by O.Iwamoto 9043 1451 16 (MF3/MT19-21,38) deleted 9043 1451 17 (MF8/MT4,16-18,37,102) added 9043 1451 18 9043 1451 19 9043 1451 20 MF=1 General information 9043 1451 21 MT=452 Number of Neutrons per fission 9043 1451 22 Sum of MT's=455 and 456. 9043 1451 23 9043 1451 24 MT=455 Delayed neutron data 9043 1451 25 Average values of systematics of Tuttle/2/, Benedetti et 9043 1451 26 al./3/ and Waldo et al./4/ 9043 1451 27 9043 1451 28 MT=456 Number of prompt neutrons per fission 9043 1451 29 Based on the semi-empirical formula of Ohsawa/5/. 9043 1451 30 9043 1451 31 9043 1451 32 MF= 2 Resonance parameters 9043 1451 33 MT=151 9043 1451 34 No resonance parameters are given. 9043 1451 35 9043 1451 36 9043 1451 37 Thermal cross sections and resonance integrals (at 300K) 9043 1451 38 ------------------------------------------------------- 9043 1451 39 0.0253 eV reson. integ.(*) 9043 1451 40 (barns) (barns) 9043 1451 41 ------------------------------------------------------- 9043 1451 42 total 1318.0 9043 1451 43 elastic 12.03 9043 1451 44 fission 15.01 115 9043 1451 45 capture 1290.6 574 9043 1451 46 ------------------------------------------------------- 9043 1451 47 (*) In the energy range from 0.5 eV to 10 MeV. 9043 1451 48 9043 1451 49 9043 1451 50 MF= 3 Neutron cross sections 9043 1451 51 Below 1.9 eV: 9043 1451 52 Elastic scattering cross section is 12.0 b calculated from 9043 1451 53 scattering radius/6/. 9043 1451 54 Fission cross section is in the 1/v shape, and 15 b at 9043 1451 55 0.0253 eV/7/. 9043 1451 56 Capture cross section is also in the 1/v shape, and 1290 b 9043 1451 57 at 0.0253 eV/8,9/. 9043 1451 58 9043 1451 59 Above 1.9 eV: 9043 1451 60 Cross sections were calculated with CCONE code/6/. 9043 1451 61 9043 1451 62 MT= 1 Total cross section 9043 1451 63 The cross section was calculated with CC OMP of Soukhovitskii 9043 1451 64 et al./10/. 9043 1451 65 9043 1451 66 9043 1451 67 MF= 4 Angular distributions of secondary neutrons 9043 1451 68 MT=2 Elastic scattering 9043 1451 69 Calculated with CCONE code/6/. 9043 1451 70 9043 1451 71 MT=18 Fission 9043 1451 72 Isotropic distributions in the laboratory system were assumed.9043 1451 73 9043 1451 74 9043 1451 75 MF= 5 Energy distributions of secondary neutrons 9043 1451 76 MT=18 Prompt neutrons 9043 1451 77 Calculated with CCONE code/6/. 9043 1451 78 9043 1451 79 9043 1451 80 MF= 6 Energy-angle distributions 9043 1451 81 Calculated with CCONE code/6/. 9043 1451 82 Distributions from fission (MT=18) are not included. 9043 1451 83 9043 1451 84 9043 1451 85 MF=12 Photon production multiplicities 9043 1451 86 MT=18 Fission 9043 1451 87 Calculated from the total energy released by the prompt 9043 1451 88 gamma-rays due to fission which was estimated from its 9043 1451 89 systematics, and the average energy of gamma-rays. 9043 1451 90 9043 1451 91 9043 1451 92 MF=14 Photon angular distributions 9043 1451 93 MT=18 Fission 9043 1451 94 Isotoropic distributions were assumed. 9043 1451 95 9043 1451 96 9043 1451 97 MF=15 Continuous photon energy spectra 9043 1451 98 MT=18 Fission 9043 1451 99 Experimental data measured by Verbinski et al./11/ for 9043 1451 100 U-235 thermal fission were adopted. 9043 1451 101 9043 1451 102 9043 1451 103 MF=31 Covariances of average number of neutrons per fission 9043 1451 104 MT=452 Number of neutrons per fission 9043 1451 105 Sum of covariances for MT=455 and MT=456. 9043 1451 106 9043 1451 107 MT=455 9043 1451 108 Error of 15% was assumed. 9043 1451 109 9043 1451 110 MT=456 9043 1451 111 Covariance was obtained by fitting a linear function to the 9043 1451 112 at 0.0 and 5.0 MeV with an uncertainty of 5%. 9043 1451 113 9043 1451 114 9043 1451 115 MF=33 Covariances of neutron cross sections 9043 1451 116 Covariances were given to all the cross sections by using 9043 1451 117 KALMAN code/12/ and the covariances of model parameters 9043 1451 118 used in the cross-section calculations. 9043 1451 119 9043 1451 120 For the following cross sections, standard deviations in the 9043 1451 121 energy region below 1.9 eV were assumed as follows: 9043 1451 122 9043 1451 123 Total 44 % 9043 1451 124 Elastic scattering 50 % 9043 1451 125 Fission 50 % 9043 1451 126 Capture 44 % estimated from experimental data 9043 1451 127 9043 1451 128 9043 1451 129 MF=34 Covariances for Angular Distributions 9043 1451 130 MT=2 Elastic scattering 9043 1451 131 Covariances were given only to P1 components. 9043 1451 132 9043 1451 133 9043 1451 134 MF=35 Covariances for Energy Distributions 9043 1451 135 MT=18 Fission spectra 9043 1451 136 Estimated with CCONE and KALMAN codes. 9043 1451 137 9043 1451 138 9043 1451 139 ***************************************************************** 9043 1451 140 Calculation with CCONE code 9043 1451 141 ***************************************************************** 9043 1451 142 9043 1451 143 Models and parameters used in the CCONE/6/ calculation 9043 1451 144 1) Coupled channel optical model 9043 1451 145 Levels in the rotational band were included. Optical model 9043 1451 146 potential and coupled levels are shown in Table 1. 9043 1451 147 9043 1451 148 2) Two-component exciton model/13/ 9043 1451 149 * Global parametrization of Koning-Duijvestijn/14/ 9043 1451 150 was used. 9043 1451 151 * Gamma emission channel/15/ was added to simulate direct 9043 1451 152 and semi-direct capture reaction. 9043 1451 153 9043 1451 154 3) Hauser-Feshbach statistical model 9043 1451 155 * Moldauer width fluctuation correction/16/ was included. 9043 1451 156 * Neutron, gamma and fission decay channel were included. 9043 1451 157 * Transmission coefficients of neutrons were taken from 9043 1451 158 coupled channel calculation in Table 1. 9043 1451 159 * The level scheme of the target is shown in Table 2. 9043 1451 160 * Level density formula of constant temperature and Fermi-gas 9043 1451 161 model were used with shell energy correction and collective 9043 1451 162 enhancement factor. Parameters are shown in Table 3. 9043 1451 163 * Fission channel: 9043 1451 164 Double humped fission barriers were assumed. 9043 1451 165 Fission barrier penetrabilities were calculated with 9043 1451 166 Hill-Wheler formula/17/. Fission barrier parameters were 9043 1451 167 shown in Table 4. Transition state model was used and 9043 1451 168 continuum levels are assumed above the saddles. The level 9043 1451 169 density parameters for inner and outer saddles are shown in 9043 1451 170 Tables 5 and 6, respectively. 9043 1451 171 * Gamma-ray strength function of Kopecky et al/18/,/19/ 9043 1451 172 was used. The prameters are shown in Table 7. 9043 1451 173 9043 1451 174 9043 1451 175 ------------------------------------------------------------------9043 1451 176 Tables 9043 1451 177 ------------------------------------------------------------------9043 1451 178 9043 1451 179 Table 1. Coupled channel calculation 9043 1451 180 -------------------------------------------------- 9043 1451 181 * rigid rotor model was applied 9043 1451 182 * coupled levels = 0,3,5,6,9 (see Table 2) 9043 1451 183 * optical potential parameters /10/ 9043 1451 184 Volume: 9043 1451 185 V_0 = 49.97 MeV 9043 1451 186 lambda_HF = 0.01004 1/MeV 9043 1451 187 C_viso = 15.9 MeV 9043 1451 188 A_v = 12.04 MeV 9043 1451 189 B_v = 81.36 MeV 9043 1451 190 E_a = 385 MeV 9043 1451 191 r_v = 1.2568 fm 9043 1451 192 a_v = 0.633 fm 9043 1451 193 Surface: 9043 1451 194 W_0 = 17.2 MeV 9043 1451 195 B_s = 11.19 MeV 9043 1451 196 C_s = 0.01361 1/MeV 9043 1451 197 C_wiso = 23.5 MeV 9043 1451 198 r_s = 1.1803 fm 9043 1451 199 a_s = 0.601 fm 9043 1451 200 Spin-orbit: 9043 1451 201 V_so = 5.75 MeV 9043 1451 202 lambda_so = 0.005 1/MeV 9043 1451 203 W_so = -3.1 MeV 9043 1451 204 B_so = 160 MeV 9043 1451 205 r_so = 1.1214 fm 9043 1451 206 a_so = 0.59 fm 9043 1451 207 Coulomb: 9043 1451 208 C_coul = 1.3 9043 1451 209 r_c = 1.2452 fm 9043 1451 210 a_c = 0.545 fm 9043 1451 211 Deformation: 9043 1451 212 beta_2 = 0.213 9043 1451 213 beta_4 = 0.066 9043 1451 214 beta_6 = 0.0015 9043 1451 215 9043 1451 216 * Calculated strength function 9043 1451 217 S0= 0.78e-4 S1= 1.48e-4 R'= 9.72 fm (En=1 keV) 9043 1451 218 -------------------------------------------------- 9043 1451 219 9043 1451 220 Table 2. Level Scheme of Th-233 9043 1451 221 ------------------- 9043 1451 222 No. Ex(MeV) J PI 9043 1451 223 ------------------- 9043 1451 224 0 0.00000 1/2 + * 9043 1451 225 1 0.00604 5/2 + 9043 1451 226 2 0.00606 7/2 - 9043 1451 227 3 0.01686 3/2 + * 9043 1451 228 4 0.05038 7/2 + 9043 1451 229 5 0.05455 5/2 + * 9043 1451 230 6 0.09362 7/2 + * 9043 1451 231 7 0.10734 9/2 + 9043 1451 232 8 0.14410 11/2 - 9043 1451 233 9 0.15800 9/2 + * 9043 1451 234 10 0.17800 11/2 + 9043 1451 235 11 0.22000 11/2 + 9043 1451 236 12 0.25230 15/2 - 9043 1451 237 13 0.26224 5/2 + 9043 1451 238 14 0.27940 7/2 + 9043 1451 239 15 0.30950 1/2 + 9043 1451 240 16 0.31320 13/2 + 9043 1451 241 17 0.31870 15/2 - 9043 1451 242 18 0.32600 9/2 + 9043 1451 243 19 0.33593 3/2 + 9043 1451 244 20 0.33735 5/2 - 9043 1451 245 ------------------- 9043 1451 246 *) Coupled levels in CC calculation 9043 1451 247 9043 1451 248 Table 3. Level density parameters 9043 1451 249 -------------------------------------------------------- 9043 1451 250 Nuclide a* Pair Eshell T E0 Ematch 9043 1451 251 1/MeV MeV MeV MeV MeV MeV 9043 1451 252 -------------------------------------------------------- 9043 1451 253 Th-234 18.1029 1.5689 3.6260 0.3733 -0.0455 3.7635 9043 1451 254 Th-233 18.8481 0.7861 3.5545 0.3805 -1.0048 3.1955 9043 1451 255 Th-232 18.7786 1.5757 3.3953 0.3835 -0.2200 3.9949 9043 1451 256 Th-231 18.7090 0.7895 3.3191 0.3770 -0.9082 3.0943 9043 1451 257 Th-230 18.6395 1.5825 3.2401 0.4059 -0.4442 4.2813 9043 1451 258 -------------------------------------------------------- 9043 1451 259 9043 1451 260 Table 4. Fission barrier parameters 9043 1451 261 ---------------------------------------- 9043 1451 262 Nuclide V_A hw_A V_B hw_B 9043 1451 263 MeV MeV MeV MeV 9043 1451 264 ---------------------------------------- 9043 1451 265 Th-234 5.800 1.040 5.950 0.500 9043 1451 266 Th-233 5.820 1.000 6.150 0.530 9043 1451 267 Th-232 5.800 1.040 5.950 0.500 9043 1451 268 Th-231 6.000 0.800 6.000 0.600 9043 1451 269 Th-230 5.500 1.040 5.950 0.600 9043 1451 270 ---------------------------------------- 9043 1451 271 9043 1451 272 Table 5. Level density above inner saddle 9043 1451 273 -------------------------------------------------------- 9043 1451 274 Nuclide a* Pair Eshell T E0 Ematch 9043 1451 275 1/MeV MeV MeV MeV MeV MeV 9043 1451 276 -------------------------------------------------------- 9043 1451 277 Th-234 20.2753 1.8304 2.6000 0.3306 -0.5810 3.8304 9043 1451 278 Th-233 20.2008 0.9172 2.6000 0.3312 -1.4942 2.9172 9043 1451 279 Th-232 20.1263 1.8383 2.6000 0.3319 -0.5731 3.8383 9043 1451 280 Th-231 19.6937 0.9211 2.6000 0.3507 -1.7165 3.1211 9043 1451 281 Th-230 19.9772 1.8463 2.6000 0.3332 -0.5651 3.8463 9043 1451 282 -------------------------------------------------------- 9043 1451 283 9043 1451 284 Table 6. Level density above outer saddle 9043 1451 285 -------------------------------------------------------- 9043 1451 286 Nuclide a* Pair Eshell T E0 Ematch 9043 1451 287 1/MeV MeV MeV MeV MeV MeV 9043 1451 288 -------------------------------------------------------- 9043 1451 289 Th-234 20.2753 1.8304 -0.0600 0.3733 0.1314 3.8304 9043 1451 290 Th-233 20.7419 0.9172 -0.1000 0.3835 -0.9412 3.1172 9043 1451 291 Th-232 20.5756 1.8383 -0.1400 0.3595 0.2690 3.6883 9043 1451 292 Th-231 19.6937 0.9211 -0.1800 0.3963 -0.9457 3.1211 9043 1451 293 Th-230 19.9772 1.8463 -0.2200 0.3786 0.1497 3.8463 9043 1451 294 -------------------------------------------------------- 9043 1451 295 9043 1451 296 Table 7. Gamma-ray strength function for Th-234 9043 1451 297 -------------------------------------------------------- 9043 1451 298 K0 = 1.501 E0 = 4.500 (MeV) 9043 1451 299 * E1: ER = 11.03 (MeV) EG = 2.71 (MeV) SIG = 302.00 (mb) 9043 1451 300 ER = 13.87 (MeV) EG = 4.77 (MeV) SIG = 449.00 (mb) 9043 1451 301 * M1: ER = 6.65 (MeV) EG = 4.00 (MeV) SIG = 2.77 (mb) 9043 1451 302 * E2: ER = 10.22 (MeV) EG = 3.30 (MeV) SIG = 6.24 (mb) 9043 1451 303 -------------------------------------------------------- 9043 1451 304 9043 1451 305 9043 1451 306 References 9043 1451 307 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9043 1451 308 2) R.J.Tuttle: INDC(NDS)-107/G+SPECIAL, P.29 (1979), 9043 1451 309 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 9043 1451 310 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 9043 1451 311 5) T.Ohsawa: J. Nucl. Radiochem. Sci., 9, 19 (2008). 9043 1451 312 6) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9043 1451 313 7) S.F.Mughabghab: "Atlas of Neutron Resonances," Elsevier 9043 1451 314 (2006). 9043 1451 315 8) H.Chatani: 2004 Santa Fe, Vol.1, p.664 (2004). 9043 1451 316 9) F.J.Johnston et al.: J. Nucl. Energy, A11, 95 (1960). 9043 1451 317 10) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9043 1451 318 11) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9043 1451 319 12) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9043 1451 320 Japanese. 9043 1451 321 13) C.Kalbach: Phys. Rev. C33, 818 (1986). 9043 1451 322 14) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9043 1451 323 15) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9043 1451 324 16) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9043 1451 325 17) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9043 1451 326 18) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9043 1451 327 19) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9043 1451 328 9043 1451 329 1 451 343 19043 1451 330 2 151 4 19043 1451 331 3 4 33 19043 1451 332 3 16 14 19043 1451 333 3 17 9 19043 1451 334 3 18 146 19043 1451 335 3 37 6 19043 1451 336 3 102 150 19043 1451 337 8 4 2 19043 1451 338 8 16 2 19043 1451 339 8 17 2 19043 1451 340 8 18 2 19043 1451 341 8 37 2 19043 1451 342 8 102 2 19043 1451 343 9043 1 099999 9043 0 0 0 9.023300+4 2.310400+2 0 0 1 09043 2151 1 9.023300+4 1.000000+0 0 0 1 09043 2151 2 1.000000-5 1.900000+0 0 0 0 09043 2151 3 5.000000-1 9.765000-1 0 0 0 09043 2151 4 9043 2 099999 9043 0 0 0 9.023300+4 2.310400+2 0 0 0 09043 3 4 1 0.000000+0-6.040000+3 0 0 1 899043 3 4 2 89 2 9043 3 4 3 6.066140+3 0.000000+0 6.086230+3 2.348330-5 7.000000+3 6.384370-49043 3 4 4 1.000000+4 5.150121-3 1.693300+4 2.437043-2 2.000000+4 2.067863-19043 3 4 5 3.000000+4 3.191346-1 5.000000+4 4.531833-1 5.059810+4 4.563935-19043 3 4 6 5.478210+4 4.803431-1 7.000000+4 5.878537-1 9.402520+4 7.333057-19043 3 4 7 1.000000+5 7.716056-1 1.048040+5 7.885354-1 1.078050+5 7.991208-19043 3 4 8 1.200000+5 8.426452-1 1.400000+5 9.184372-1 1.447240+5 9.377007-19043 3 4 9 1.586840+5 9.975510-1 1.700000+5 1.049187+0 1.787700+5 1.091374+09043 3 4 10 2.000000+5 1.201309+0 2.209520+5 1.245712+0 2.500000+5 1.319541+09043 3 4 11 2.533920+5 1.329232+0 2.633750+5 1.358539+0 2.806090+5 1.418724+09043 3 4 12 3.000000+5 1.494012+0 3.108400+5 1.506635+0 3.145560+5 1.523910+09043 3 4 13 3.200790+5 1.537277+0 3.274110+5 1.552710+0 3.373820+5 1.573100+09043 3 4 14 3.388100+5 1.580167+0 4.000000+5 1.757212+0 5.000000+5 2.109658+09043 3 4 15 6.000000+5 2.314101+0 7.000000+5 2.556706+0 8.000000+5 2.720559+09043 3 4 16 9.000000+5 2.882373+0 1.000000+6 3.046646+0 1.100000+6 3.179526+09043 3 4 17 1.200000+6 3.302092+0 1.300000+6 3.414647+0 1.400000+6 3.515639+09043 3 4 18 1.500000+6 3.601862+0 1.600000+6 3.678869+0 1.700000+6 3.735710+09043 3 4 19 1.800000+6 3.785470+0 1.900000+6 3.815608+0 2.000000+6 3.840300+09043 3 4 20 2.300000+6 3.851074+0 2.500000+6 3.826960+0 2.700000+6 3.791461+09043 3 4 21 3.000000+6 3.723714+0 3.500000+6 3.604507+0 4.000000+6 3.486471+09043 3 4 22 4.500000+6 3.379716+0 5.000000+6 3.279526+0 5.500000+6 2.668247+09043 3 4 23 6.000000+6 1.987304+0 6.500000+6 1.504004+0 7.000000+6 1.183915+09043 3 4 24 7.500000+6 9.711238-1 8.000000+6 8.336930-1 8.500000+6 7.373634-19043 3 4 25 9.000000+6 6.703252-1 9.500000+6 6.191780-1 1.000000+7 5.799052-19043 3 4 26 1.050000+7 5.482435-1 1.100000+7 5.223034-1 1.150000+7 4.994751-19043 3 4 27 1.200000+7 4.776706-1 1.250000+7 4.593655-1 1.300000+7 4.412164-19043 3 4 28 1.350000+7 4.253081-1 1.400000+7 4.082156-1 1.450000+7 3.935709-19043 3 4 29 1.500000+7 3.787334-1 1.550000+7 3.658210-1 1.600000+7 3.529919-19043 3 4 30 1.650000+7 3.413790-1 1.700000+7 3.299033-1 1.750000+7 3.200756-19043 3 4 31 1.800000+7 3.102136-1 1.850000+7 3.011786-1 1.900000+7 2.916303-19043 3 4 32 1.950000+7 2.837724-1 2.000000+7 2.772303-1 9043 3 4 33 9043 3 099999 9.023300+4 2.310400+2 0 0 0 09043 3 16 1 -4.786390+6-4.786390+6 0 0 1 329043 3 16 2 32 2 9043 3 16 3 4.807100+6 0.000000+0 5.000000+6 2.425330-2 5.500000+6 5.656070-19043 3 16 4 6.000000+6 1.212950+0 6.500000+6 1.662790+0 7.000000+6 1.955500+09043 3 16 5 7.500000+6 2.130740+0 8.000000+6 2.255250+0 8.500000+6 2.328100+09043 3 16 6 9.000000+6 2.386350+0 9.500000+6 2.418140+0 1.000000+7 2.444050+09043 3 16 7 1.050000+7 2.457280+0 1.100000+7 2.466130+0 1.150000+7 2.463560+09043 3 16 8 1.200000+7 2.425670+0 1.250000+7 2.313620+0 1.300000+7 2.115080+09043 3 16 9 1.350000+7 1.867040+0 1.400000+7 1.603120+0 1.450000+7 1.349520+09043 3 16 10 1.500000+7 1.123800+0 1.550000+7 9.570790-1 1.600000+7 8.215150-19043 3 16 11 1.650000+7 6.989710-1 1.700000+7 6.184390-1 1.750000+7 5.560780-19043 3 16 12 1.800000+7 5.083920-1 1.850000+7 4.787240-1 1.900000+7 4.490050-19043 3 16 13 1.950000+7 4.247110-1 2.000000+7 4.072750-1 9043 3 16 14 9043 3 099999 9.023300+4 2.310400+2 0 0 0 09043 3 17 1 -1.122670+7-1.122670+7 0 0 1 189043 3 17 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