JENDL-5 (Neutron sublibrary (activation cs)) Pa-229 0 0 0 0 9.122900+4 2.270650+2 0 0 6 19125 1451 1 0.000000+0 1.000000+0 0 0 0 69125 1451 2 1.000000+0 2.000000+7 0 0 10 59125 1451 3 2.936000+2 0.000000+0 4 0 325 129125 1451 4 91-Pa-229 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9125 1451 5 DIST-DEC21 20100304 9125 1451 6 ----JENDL-5 MATERIAL 9125 9125 1451 7 -----INCIDENT NEUTRON DATA 9125 1451 8 ------ENDF-6 FORMAT 9125 1451 9 9125 1451 10 History 9125 1451 11 07-10 Theoretical calculation was performed with CCONE code. 9125 1451 12 Data were compiled as JENDL/AC-2008/1/. 9125 1451 13 10-02 Data of prompt gamma rays due to fission were given. 9125 1451 14 10-03 Covariance data were given. 9125 1451 15 21-11 revised by O.Iwamoto 9125 1451 16 (MF3/MT19-21,38) deleted 9125 1451 17 (MF8/MT4,16-18,102) added 9125 1451 18 9125 1451 19 9125 1451 20 MF=1 General information 9125 1451 21 MT=452 Number of Neutrons per fission 9125 1451 22 Sum of MT's=455 and 456. 9125 1451 23 9125 1451 24 MT=455 Delayed neutron data 9125 1451 25 Estimated from systematics by Tuttle/2/, Benedetti et al./3/ 9125 1451 26 and Waldo et al./4/ 9125 1451 27 9125 1451 28 MT=456 Number of prompt neutrons per fission 9125 1451 29 Estimated from Howerton's systematics/5/. 9125 1451 30 9125 1451 31 9125 1451 32 MF= 2 Resonance parameters 9125 1451 33 MT=151 9125 1451 34 No resonance parameters are given. 9125 1451 35 9125 1451 36 9125 1451 37 Thermal cross sections and resonance integrals (at 300K) 9125 1451 38 ------------------------------------------------------- 9125 1451 39 0.0253 eV reson. integ.(*) 9125 1451 40 (barns) (barns) 9125 1451 41 ------------------------------------------------------- 9125 1451 42 total 413.0 9125 1451 43 elastic 11.83 9125 1451 44 fission 1.000 20.5 9125 1451 45 capture 399.9 757 9125 1451 46 ------------------------------------------------------- 9125 1451 47 (*) In the energy range from 0.5 eV to 10 MeV. 9125 1451 48 9125 1451 49 9125 1451 50 MF= 3 Neutron cross sections 9125 1451 51 Below 0.15 eV: 9125 1451 52 * Elastic scattering cross section is 11.8 b calculated from 9125 1451 53 scattering radius of 9.691 fm/6/. 9125 1451 54 * Fission cross section is in the 1/v shape. 9125 1451 55 1 b at 0.0253 eV was estimated from systematics. 9125 1451 56 * Capture cross section is in the 1/v shape. 9125 1451 57 Cross section of 400 b at 0.0253 eV was estimated from 9125 1451 58 systematics. 9125 1451 59 9125 1451 60 Above 0.15 eV: 9125 1451 61 Cross sections calculated with CCONE code/6/ were adopted 9125 1451 62 except for total(MT=1) and fission(MT=18) cross sections. 9125 1451 63 9125 1451 64 MT=1 Total cross section 9125 1451 65 The cross section was calculated with CC OMP of Soukhovitskii 9125 1451 66 et al./7/. 9125 1451 67 After correction of the fission cross section mentioned 9125 1451 68 below, the total cross section was calculated as a sum of 9125 1451 69 partial cross sections. 9125 1451 70 9125 1451 71 MT=18 Fission cross section 9125 1451 72 Between 0.15 and 3 eV, 1/v-shape cross section was roughly 9125 1451 73 assumed. 9125 1451 74 From 3 eV to 10 keV, a constant value of 0.9 b was assumed. 9125 1451 75 Above 30 keV, CCONE calculation was adopted. 9125 1451 76 The simulated (n,f) cross sections measured by Britt and 9125 1451 77 Wilhelmy/8/ were used to determine the parameters in the 9125 1451 78 CCONE calculation. 9125 1451 79 9125 1451 80 9125 1451 81 MF= 4 Angular distributions of secondary neutrons 9125 1451 82 MT=2 Elastic scattering 9125 1451 83 Calculated with CCONE code/6/. 9125 1451 84 9125 1451 85 MT=18 Fission 9125 1451 86 Isotropic distributions in the laboratory system were assumed.9125 1451 87 9125 1451 88 9125 1451 89 MF= 5 Energy distributions of secondary neutrons 9125 1451 90 MT=18 Prompt neutrons 9125 1451 91 Calculated with CCONE code/6/. 9125 1451 92 9125 1451 93 9125 1451 94 MF= 6 Energy-angle distributions 9125 1451 95 Calculated with CCONE code/6/. 9125 1451 96 Distributions from fission (MT=18) are not included. 9125 1451 97 9125 1451 98 9125 1451 99 MF=12 Photon production multiplicities 9125 1451 100 MT=18 Fission 9125 1451 101 Calculated from the total energy released by the prompt 9125 1451 102 gamma-rays due to fission which was estimated from its 9125 1451 103 systematics, and the average energy of gamma-rays. 9125 1451 104 9125 1451 105 9125 1451 106 MF=14 Photon angular distributions 9125 1451 107 MT=18 Fission 9125 1451 108 Isotoropic distributions were assumed. 9125 1451 109 9125 1451 110 9125 1451 111 MF=15 Continuous photon energy spectra 9125 1451 112 MT=18 Fission 9125 1451 113 Experimental data measured by Verbinski et al./9/ for 9125 1451 114 U-235 thermal fission were adopted. 9125 1451 115 9125 1451 116 9125 1451 117 MF=31 Covariances of average number of neutrons per fission 9125 1451 118 MT=452 Number of neutrons per fission 9125 1451 119 Sum of covariances for MT=455 and MT=456. 9125 1451 120 9125 1451 121 MT=455 9125 1451 122 Error of 15% was assumed. 9125 1451 123 9125 1451 124 MT=456 9125 1451 125 Covariance was obtained by fitting a linear function to the 9125 1451 126 at 0.0 and 5.0 MeV with an uncertainty of 5%. 9125 1451 127 9125 1451 128 9125 1451 129 MF=33 Covariances of neutron cross sections 9125 1451 130 Covariances were given to all the cross sections by using 9125 1451 131 KALMAN code/10/ and the covariances of model parameters 9125 1451 132 used in the cross-section calculations. 9125 1451 133 9125 1451 134 Covariances of the fission cross section were determined from 9125 1451 135 experimental data. 9125 1451 136 9125 1451 137 For the following cross sections, standard deviations in the 9125 1451 138 energy region below 0.15 eV were assumed as follows: 9125 1451 139 9125 1451 140 Total 87 % 9125 1451 141 Elastic scattering 90 % 9125 1451 142 Fission 90 % 9125 1451 143 Capture 90 % 9125 1451 144 9125 1451 145 9125 1451 146 MF=34 Covariances for Angular Distributions 9125 1451 147 MT=2 Elastic scattering 9125 1451 148 Covariances were given only to P1 components. 9125 1451 149 9125 1451 150 9125 1451 151 MF=35 Covariances for Energy Distributions 9125 1451 152 MT=18 Fission spectra 9125 1451 153 Estimated with CCONE and KALMAN codes. 9125 1451 154 9125 1451 155 9125 1451 156 ***************************************************************** 9125 1451 157 Calculation with CCONE code 9125 1451 158 ***************************************************************** 9125 1451 159 9125 1451 160 Models and parameters used in the CCONE/6/ calculation 9125 1451 161 1) Coupled channel optical model 9125 1451 162 Levels in the rotational band were included. Optical model 9125 1451 163 potential and coupled levels are shown in Table 1. 9125 1451 164 9125 1451 165 2) Two-component exciton model/11/ 9125 1451 166 * Global parametrization of Koning-Duijvestijn/12/ 9125 1451 167 was used. 9125 1451 168 * Gamma emission channel/13/ was added to simulate direct 9125 1451 169 and semi-direct capture reaction. 9125 1451 170 9125 1451 171 3) Hauser-Feshbach statistical model 9125 1451 172 * Moldauer width fluctuation correction/14/ was included. 9125 1451 173 * Neutron, gamma and fission decay channel were included. 9125 1451 174 * Transmission coefficients of neutrons were taken from 9125 1451 175 coupled channel calculation in Table 1. 9125 1451 176 * The level scheme of the target is shown in Table 2. 9125 1451 177 * Level density formula of constant temperature and Fermi-gas 9125 1451 178 model were used with shell energy correction and collective 9125 1451 179 enhancement factor. Parameters are shown in Table 3. 9125 1451 180 * Fission channel: 9125 1451 181 Double humped fission barriers were assumed. 9125 1451 182 Fission barrier penetrabilities were calculated with 9125 1451 183 Hill-Wheler formula/15/. Fission barrier parameters were 9125 1451 184 shown in Table 4. Transition state model was used and 9125 1451 185 continuum levels are assumed above the saddles. The level 9125 1451 186 density parameters for inner and outer saddles are shown in 9125 1451 187 Tables 5 and 6, respectively. 9125 1451 188 * Gamma-ray strength function of Kopecky et al/16/,/17/ 9125 1451 189 was used. The prameters are shown in Table 7. 9125 1451 190 9125 1451 191 9125 1451 192 ------------------------------------------------------------------9125 1451 193 Tables 9125 1451 194 ------------------------------------------------------------------9125 1451 195 9125 1451 196 Table 1. Coupled channel calculation 9125 1451 197 -------------------------------------------------- 9125 1451 198 * rigid rotor model was applied 9125 1451 199 * coupled levels = 0,2,5,10 (see Table 2) 9125 1451 200 * optical potential parameters /7/ 9125 1451 201 Volume: 9125 1451 202 V_0 = 49.97 MeV 9125 1451 203 lambda_HF = 0.01004 1/MeV 9125 1451 204 C_viso = 15.9 MeV 9125 1451 205 A_v = 12.04 MeV 9125 1451 206 B_v = 81.36 MeV 9125 1451 207 E_a = 385 MeV 9125 1451 208 r_v = 1.2568 fm 9125 1451 209 a_v = 0.633 fm 9125 1451 210 Surface: 9125 1451 211 W_0 = 17.2 MeV 9125 1451 212 B_s = 11.19 MeV 9125 1451 213 C_s = 0.01361 1/MeV 9125 1451 214 C_wiso = 23.5 MeV 9125 1451 215 r_s = 1.1803 fm 9125 1451 216 a_s = 0.601 fm 9125 1451 217 Spin-orbit: 9125 1451 218 V_so = 5.75 MeV 9125 1451 219 lambda_so = 0.005 1/MeV 9125 1451 220 W_so = -3.1 MeV 9125 1451 221 B_so = 160 MeV 9125 1451 222 r_so = 1.1214 fm 9125 1451 223 a_so = 0.59 fm 9125 1451 224 Coulomb: 9125 1451 225 C_coul = 1.3 9125 1451 226 r_c = 1.2452 fm 9125 1451 227 a_c = 0.545 fm 9125 1451 228 Deformation: 9125 1451 229 beta_2 = 0.19 9125 1451 230 beta_4 = 0.066 9125 1451 231 beta_6 = 0.0015 9125 1451 232 9125 1451 233 * Calculated strength function 9125 1451 234 S0= 0.88e-4 S1= 2.14e-4 R'= 9.69 fm (En=1 keV) 9125 1451 235 -------------------------------------------------- 9125 1451 236 9125 1451 237 Table 2. Level Scheme of Pa-229 9125 1451 238 ------------------- 9125 1451 239 No. Ex(MeV) J PI 9125 1451 240 ------------------- 9125 1451 241 0 0.00000 5/2 + * 9125 1451 242 1 0.00016 5/2 - 9125 1451 243 2 0.07300 7/2 + * 9125 1451 244 3 0.12267 3/2 - 9125 1451 245 4 0.14000 1/2 - 9125 1451 246 5 0.16686 9/2 + * 9125 1451 247 6 0.18700 7/2 - 9125 1451 248 7 0.21109 3/2 + 9125 1451 249 8 0.21700 5/2 - 9125 1451 250 9 0.24191 3/2 + 9125 1451 251 10 0.28157 11/2 + * 9125 1451 252 ------------------- 9125 1451 253 *) Coupled levels in CC calculation 9125 1451 254 9125 1451 255 Table 3. Level density parameters 9125 1451 256 -------------------------------------------------------- 9125 1451 257 Nuclide a* Pair Eshell T E0 Ematch 9125 1451 258 1/MeV MeV MeV MeV MeV MeV 9125 1451 259 -------------------------------------------------------- 9125 1451 260 Pa-230 17.8368 0.0000 2.9470 0.2794 -0.6728 1.0000 9125 1451 261 Pa-229 17.7702 0.7930 3.0707 0.3881 -0.8689 3.0597 9125 1451 262 Pa-228 17.7035 0.0000 2.9095 0.2810 -0.6716 1.0000 9125 1451 263 Pa-227 17.6369 0.7965 2.9512 0.3860 -0.8068 2.9965 9125 1451 264 -------------------------------------------------------- 9125 1451 265 9125 1451 266 Table 4. Fission barrier parameters 9125 1451 267 ---------------------------------------- 9125 1451 268 Nuclide V_A hw_A V_B hw_B 9125 1451 269 MeV MeV MeV MeV 9125 1451 270 ---------------------------------------- 9125 1451 271 Pa-230 5.800 0.800 5.900 0.400 9125 1451 272 Pa-229 6.000 0.800 5.800 0.520 9125 1451 273 Pa-228 5.800 0.800 6.180 0.400 9125 1451 274 Pa-227 6.000 0.800 5.800 0.520 9125 1451 275 ---------------------------------------- 9125 1451 276 9125 1451 277 Table 5. Level density above inner saddle 9125 1451 278 -------------------------------------------------------- 9125 1451 279 Nuclide a* Pair Eshell T E0 Ematch 9125 1451 280 1/MeV MeV MeV MeV MeV MeV 9125 1451 281 -------------------------------------------------------- 9125 1451 282 Pa-230 20.5123 0.0000 2.6000 0.3428 -2.6080 2.2000 9125 1451 283 Pa-229 20.4357 0.9251 2.6000 0.3435 -1.6829 3.1251 9125 1451 284 Pa-228 20.3591 0.0000 2.6000 0.3442 -2.6080 2.2000 9125 1451 285 Pa-227 20.2824 0.9292 2.6000 0.3449 -1.6787 3.1292 9125 1451 286 -------------------------------------------------------- 9125 1451 287 9125 1451 288 Table 6. Level density above outer saddle 9125 1451 289 -------------------------------------------------------- 9125 1451 290 Nuclide a* Pair Eshell T E0 Ematch 9125 1451 291 1/MeV MeV MeV MeV MeV MeV 9125 1451 292 -------------------------------------------------------- 9125 1451 293 Pa-230 20.5123 0.0000 -0.1600 0.3867 -1.8562 2.2000 9125 1451 294 Pa-229 20.4357 0.9251 -0.2000 0.3880 -0.9302 3.1251 9125 1451 295 Pa-228 20.3591 0.0000 -0.2400 0.3894 -1.8544 2.2000 9125 1451 296 Pa-227 20.2824 0.9292 -0.2800 0.3908 -0.9243 3.1292 9125 1451 297 -------------------------------------------------------- 9125 1451 298 9125 1451 299 Table 7. Gamma-ray strength function for Pa-230 9125 1451 300 -------------------------------------------------------- 9125 1451 301 K0 = 1.502 E0 = 4.500 (MeV) 9125 1451 302 * E1: ER = 11.03 (MeV) EG = 2.71 (MeV) SIG = 302.00 (mb) 9125 1451 303 ER = 13.87 (MeV) EG = 4.77 (MeV) SIG = 449.00 (mb) 9125 1451 304 * M1: ER = 6.69 (MeV) EG = 4.00 (MeV) SIG = 2.80 (mb) 9125 1451 305 * E2: ER = 10.28 (MeV) EG = 3.35 (MeV) SIG = 6.40 (mb) 9125 1451 306 -------------------------------------------------------- 9125 1451 307 9125 1451 308 9125 1451 309 References 9125 1451 310 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9125 1451 311 2) R.J.Tuttle: INDC(NDS)-107/G+Special, p.29 (1979). 9125 1451 312 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 9125 1451 313 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 9125 1451 314 5) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9125 1451 315 6) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9125 1451 316 7) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9125 1451 317 8) H.C.Britt, J.B.Wilhelmy: Nucl. Sci. Eng., 72, 222 (1979). 9125 1451 318 9) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9125 1451 319 10) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9125 1451 320 Japanese. 9125 1451 321 11) C.Kalbach: Phys. Rev. C33, 818 (1986). 9125 1451 322 12) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9125 1451 323 13) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9125 1451 324 14) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9125 1451 325 15) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9125 1451 326 16) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9125 1451 327 17) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9125 1451 328 9125 1451 329 1 451 341 19125 1451 330 2 151 4 19125 1451 331 3 4 32 19125 1451 332 3 16 12 19125 1451 333 3 17 8 19125 1451 334 3 18 175 19125 1451 335 3 102 154 19125 1451 336 8 4 2 19125 1451 337 8 16 2 19125 1451 338 8 17 2 19125 1451 339 8 18 2 19125 1451 340 8 102 2 19125 1451 341 9125 1 099999 9125 0 0 0 9.122900+4 2.270650+2 0 0 1 09125 2151 1 9.122900+4 1.000000+0 0 0 1 09125 2151 2 1.000000-5 1.500000-1 0 0 0 09125 2151 3 2.500000+0 9.691000-1 0 0 0 09125 2151 4 9125 2 099999 9125 0 0 0 9.122900+4 2.270650+2 0 0 0 09125 3 4 1 0.000000+0-1.600000+2 0 0 1 879125 3 4 2 87 2 9125 3 4 3 1.607050+2 0.000000+0 2.000000+2 3.520770-4 3.000000+2 9.801680-49125 3 4 4 5.000000+2 2.230040-3 7.000000+2 3.470120-3 1.000000+3 5.303010-39125 3 4 5 2.000000+3 1.119280-2 3.000000+3 1.680200-2 5.000000+3 2.734390-29125 3 4 6 7.000000+3 3.713370-2 1.000000+4 5.063020-2 2.000000+4 8.749670-29125 3 4 7 3.000000+4 1.148860-1 5.000000+4 1.503880-1 7.000000+4 1.690930-19125 3 4 8 7.332150+4 1.703950-1 1.000000+5 2.239934-1 1.109710+5 2.320485-19125 3 4 9 1.200000+5 2.386847-1 1.232100+5 2.409695-1 1.400000+5 2.738568-19125 3 4 10 1.406170+5 2.746613-1 1.675950+5 3.125257-1 1.700000+5 3.160705-19125 3 4 11 1.878240+5 3.405040-1 2.000000+5 3.733295-1 2.120200+5 3.841870-19125 3 4 12 2.179560+5 3.925995-1 2.429750+5 4.388024-1 2.500000+5 4.512600-19125 3 4 13 2.828100+5 4.994982-1 3.000000+5 5.228820-1 4.000000+5 5.658231-19125 3 4 14 5.000000+5 6.411667-1 6.000000+5 6.694797-1 7.000000+5 7.165747-19125 3 4 15 8.000000+5 7.469212-1 9.000000+5 7.843003-1 1.000000+6 8.282036-19125 3 4 16 1.100000+6 8.693533-1 1.200000+6 9.116260-1 1.300000+6 9.548913-19125 3 4 17 1.400000+6 9.969374-1 1.500000+6 1.038057+0 1.600000+6 1.077470+09125 3 4 18 1.700000+6 1.113155+0 1.800000+6 1.147038+0 1.900000+6 1.175647+09125 3 4 19 2.000000+6 1.202571+0 2.300000+6 1.260382+0 2.500000+6 1.284734+09125 3 4 20 2.700000+6 1.305076+0 3.000000+6 1.335903+0 3.500000+6 1.400604+09125 3 4 21 4.000000+6 1.484582+0 4.500000+6 1.556927+0 5.000000+6 1.630658+09125 3 4 22 5.500000+6 1.684640+0 6.000000+6 1.675759+0 6.500000+6 1.459784+09125 3 4 23 7.000000+6 1.218193+0 7.500000+6 1.011151+0 8.000000+6 8.535637-19125 3 4 24 8.500000+6 7.283199-1 9.000000+6 6.339398-1 9.500000+6 5.601644-19125 3 4 25 1.000000+7 5.040105-1 1.050000+7 4.610738-1 1.100000+7 4.273471-19125 3 4 26 1.150000+7 4.013637-1 1.200000+7 3.797183-1 1.250000+7 3.619755-19125 3 4 27 1.300000+7 3.462035-1 1.350000+7 3.324775-1 1.400000+7 3.195981-19125 3 4 28 1.450000+7 3.080378-1 1.500000+7 2.968860-1 1.550000+7 2.868515-19125 3 4 29 1.600000+7 2.769654-1 1.650000+7 2.680318-1 1.700000+7 2.592981-19125 3 4 30 1.750000+7 2.512051-1 1.800000+7 2.433762-1 1.850000+7 2.361977-19125 3 4 31 1.900000+7 2.291646-1 1.950000+7 2.226742-1 2.000000+7 2.163481-19125 3 4 32 9125 3 099999 9.122900+4 2.270650+2 0 0 0 09125 3 16 1 -7.097520+6-7.097520+6 0 0 1 279125 3 16 2 27 2 9125 3 16 3 7.128770+6 0.000000+0 7.500000+6 1.282670-3 8.000000+6 2.347540-29125 3 16 4 8.500000+6 8.157640-2 9.000000+6 1.709030-1 9.500000+6 2.770430-19125 3 16 5 1.000000+7 3.867440-1 1.050000+7 4.867500-1 1.100000+7 5.822350-19125 3 16 6 1.150000+7 6.608180-1 1.200000+7 7.324250-1 1.250000+7 7.929950-19125 3 16 7 1.300000+7 8.458720-1 1.350000+7 8.921950-1 1.400000+7 9.251140-19125 3 16 8 1.450000+7 9.269540-1 1.500000+7 8.930990-1 1.550000+7 8.290520-19125 3 16 9 1.600000+7 7.536670-1 1.650000+7 6.669580-1 1.700000+7 5.876670-19125 3 16 10 1.750000+7 5.172830-1 1.800000+7 4.553300-1 1.850000+7 4.034240-19125 3 16 11 1.900000+7 3.608890-1 1.950000+7 3.264570-1 2.000000+7 2.987870-19125 3 16 12 9125 3 099999 9.122900+4 2.270650+2 0 0 0 09125 3 17 1 -1.307640+7-1.307640+7 0 0 1 159125 3 17 2 15 2 9125 3 17 3 1.313400+7 0.000000+0 1.350000+7 1.595470-5 1.400000+7 1.640330-39125 3 17 4 1.450000+7 7.807830-3 1.500000+7 2.116010-2 1.550000+7 4.308450-29125 3 17 5 1.600000+7 6.093870-2 1.650000+7 9.485660-2 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