JENDL-5 (Neutron sublibrary (activation cs)) Np-234 0 0 0 0 9.323400+4 2.320320+2 0 0 6 19337 1451 1 0.000000+0 1.000000+0 0 0 0 69337 1451 2 1.000000+0 2.000000+7 0 0 10 59337 1451 3 2.936000+2 0.000000+0 4 0 318 129337 1451 4 93-Np-234 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9337 1451 5 DIST-DEC21 20100304 9337 1451 6 ----JENDL-5 MATERIAL 9337 9337 1451 7 -----INCIDENT NEUTRON DATA 9337 1451 8 ------ENDF-6 FORMAT 9337 1451 9 9337 1451 10 History 9337 1451 11 07-10 Theoretical calculation was performed with CCONE code. 9337 1451 12 07-11 Data were compiled as JENDL/AC-2008/1/. 9337 1451 13 09-02 (1,452), (1,455) and (1,456) were modified. 9337 1451 14 10-02 Data of prompt gamma rays due to fission were given. 9337 1451 15 10-03 Covariance data were given. 9337 1451 16 9337 1451 17 21-11 revised by O.Iwamoto 9337 1451 18 (MF3/MT19-21,38) deleted 9337 1451 19 (MF8/MT4,16-18,102) added 9337 1451 20 9337 1451 21 MF=1 General information 9337 1451 22 MT=452 Number of Neutrons per fission 9337 1451 23 Sum of MT's=455 and 456. 9337 1451 24 9337 1451 25 MT=455 Delayed neutron data 9337 1451 26 Estimated from systematics by Tuttle/2/, Benedetti et al./3/ 9337 1451 27 and Waldo et al./4/, and partial fission cross sections 9337 1451 28 calculated with CCONE code/5/. 9337 1451 29 9337 1451 30 MT=456 Number of prompt neutrons per fission 9337 1451 31 Estimated from Ohsawa's systematics/6/. 9337 1451 32 9337 1451 33 9337 1451 34 MF= 2 Resonance parameters 9337 1451 35 MT=151 9337 1451 36 No resonance parameters are given. 9337 1451 37 9337 1451 38 9337 1451 39 Thermal cross sections and resonance integrals (at 300K) 9337 1451 40 ------------------------------------------------------- 9337 1451 41 0.0253 eV reson. integ.(*) 9337 1451 42 (barns) (barns) 9337 1451 43 ------------------------------------------------------- 9337 1451 44 total 2122.7 9337 1451 45 elastic 11.43 9337 1451 46 fission 2000.8 117 9337 1451 47 capture 110.1 63.1 9337 1451 48 ------------------------------------------------------- 9337 1451 49 (*) In the energy range from 0.5 eV to 10 MeV. 9337 1451 50 9337 1451 51 9337 1451 52 MF= 3 Neutron cross sections 9337 1451 53 Below 0.5 eV: 9337 1451 54 * Elastic scattering cross section is 11.4 b calculated from 9337 1451 55 scattering radius of 9.539 fm/5/. 9337 1451 56 * Fission cross section is in the 1/v shape. 9337 1451 57 2000 b at 0.0253 eV was estimated from systematics. 9337 1451 58 * Capture cross section is in the 1/v shape. 9337 1451 59 Cross section of 110 b at 0.0253 eV was estimated from 9337 1451 60 capture to fission ratio calculated at 1 eV with CCONE 9337 1451 61 code and fission cross section of 2000 b. 9337 1451 62 9337 1451 63 Above 0.5 eV: 9337 1451 64 Cross sections calculated with CCONE code/5/ were adopted. 9337 1451 65 9337 1451 66 MT= 1 Total cross section 9337 1451 67 The cross section was calculated with CC OMP of Soukhovitskii 9337 1451 68 et al./7/. 9337 1451 69 9337 1451 70 MT=18 Fission cross section 9337 1451 71 Calculated with CCONE code. The simulated (n,f) cross sections 9337 1451 72 of Britt and Wilhelmy/8/ were used to determine the parameters 9337 1451 73 in the CCONE calculation. 9337 1451 74 9337 1451 75 9337 1451 76 MF= 4 Angular distributions of secondary neutrons 9337 1451 77 MT=2 Elastic scattering 9337 1451 78 Calculated with CCONE code. 9337 1451 79 9337 1451 80 MT=18 Fission 9337 1451 81 Isotropic distributions in the laboratory system were assumed.9337 1451 82 9337 1451 83 9337 1451 84 MF= 5 Energy distributions of secondary neutrons 9337 1451 85 MT=18 Prompt neutrons 9337 1451 86 Calculated with CCONE code/5/. 9337 1451 87 9337 1451 88 9337 1451 89 MF= 6 Energy-angle distributions 9337 1451 90 Calculated with CCONE code. 9337 1451 91 Distributions from fission (MT=18) are not included. 9337 1451 92 9337 1451 93 9337 1451 94 MF=12 Photon production multiplicities 9337 1451 95 MT=18 Fission 9337 1451 96 Calculated from the total energy released by the prompt 9337 1451 97 gamma-rays due to fission which was estimated from its 9337 1451 98 systematics, and the average energy of gamma-rays. 9337 1451 99 9337 1451 100 9337 1451 101 MF=14 Photon angular distributions 9337 1451 102 MT=18 Fission 9337 1451 103 Isotoropic distributions were assumed. 9337 1451 104 9337 1451 105 9337 1451 106 MF=15 Continuous photon energy spectra 9337 1451 107 MT=18 Fission 9337 1451 108 Experimental data measured by Verbinski et al./9/ for 9337 1451 109 Pu-239 thermal fission were adopted. 9337 1451 110 9337 1451 111 9337 1451 112 MF=31 Covariances of average number of neutrons per fission 9337 1451 113 MT=452 Number of neutrons per fission 9337 1451 114 Sum of covariances for MT=455 and MT=456. 9337 1451 115 9337 1451 116 MT=455 9337 1451 117 Error of 15% was assumed. 9337 1451 118 9337 1451 119 MT=456 9337 1451 120 Covariance was obtained by fitting a linear function to the 9337 1451 121 at 0.0 and 5.0 MeV with an uncertainty of 5%. 9337 1451 122 9337 1451 123 9337 1451 124 MF=33 Covariances of neutron cross sections 9337 1451 125 Covariances were given to all the cross sections by using 9337 1451 126 KALMAN code/10/ and the covariances of model parameters 9337 1451 127 used in the cross-section calculations. 9337 1451 128 9337 1451 129 Covariances of the fission cross section were determined from 9337 1451 130 experimental data. 9337 1451 131 9337 1451 132 For the following cross sections, standard deviations in the 9337 1451 133 energy region below 0.5 eV were assumed as follows: 9337 1451 134 9337 1451 135 Total 85 % 9337 1451 136 Elastic scattering 90 % 9337 1451 137 Fission 90 % 9337 1451 138 Capture 90 % 9337 1451 139 9337 1451 140 9337 1451 141 MF=34 Covariances for Angular Distributions 9337 1451 142 MT=2 Elastic scattering 9337 1451 143 Covariances were given only to P1 components. 9337 1451 144 9337 1451 145 9337 1451 146 MF=35 Covariances for Energy Distributions 9337 1451 147 MT=18 Fission spectra 9337 1451 148 Estimated with CCONE and KALMAN codes. 9337 1451 149 9337 1451 150 9337 1451 151 ***************************************************************** 9337 1451 152 Calculation with CCONE code 9337 1451 153 ***************************************************************** 9337 1451 154 9337 1451 155 Models and parameters used in the CCONE/5/ calculation 9337 1451 156 1) Coupled channel optical model 9337 1451 157 Levels in the rotational band were included. Optical model 9337 1451 158 potential and coupled levels are shown in Table 1. 9337 1451 159 9337 1451 160 2) Two-component exciton model/11/ 9337 1451 161 * Global parametrization of Koning-Duijvestijn/12/ 9337 1451 162 was used. 9337 1451 163 * Gamma emission channel/13/ was added to simulate direct 9337 1451 164 and semi-direct capture reaction. 9337 1451 165 9337 1451 166 3) Hauser-Feshbach statistical model 9337 1451 167 * Moldauer width fluctuation correction/14/ was included. 9337 1451 168 * Neutron, gamma and fission decay channel were included. 9337 1451 169 * Transmission coefficients of neutrons were taken from 9337 1451 170 coupled channel calculation in Table 1. 9337 1451 171 * The level scheme of the target is shown in Table 2. 9337 1451 172 * Level density formula of constant temperature and Fermi-gas 9337 1451 173 model were used with shell energy correction and collective 9337 1451 174 enhancement factor. Parameters are shown in Table 3. 9337 1451 175 * Fission channel: 9337 1451 176 Double humped fission barriers were assumed. 9337 1451 177 Fission barrier penetrabilities were calculated with 9337 1451 178 Hill-Wheler formula/15/. Fission barrier parameters were 9337 1451 179 shown in Table 4. Transition state model was used and 9337 1451 180 continuum levels are assumed above the saddles. The level 9337 1451 181 density parameters for inner and outer saddles are shown in 9337 1451 182 Tables 5 and 6, respectively. 9337 1451 183 * Gamma-ray strength function of Kopecky et al/16/,/17/ 9337 1451 184 was used. The prameters are shown in Table 7. 9337 1451 185 9337 1451 186 9337 1451 187 ------------------------------------------------------------------9337 1451 188 Tables 9337 1451 189 ------------------------------------------------------------------9337 1451 190 9337 1451 191 Table 1. Coupled channel calculation 9337 1451 192 -------------------------------------------------- 9337 1451 193 * rigid rotor model was applied 9337 1451 194 * coupled levels = 0,1,2,3,4,5 (see Table 2) 9337 1451 195 * optical potential parameters /7/ 9337 1451 196 Volume: 9337 1451 197 V_0 = 49.97 MeV 9337 1451 198 lambda_HF = 0.01004 1/MeV 9337 1451 199 C_viso = 15.9 MeV 9337 1451 200 A_v = 12.04 MeV 9337 1451 201 B_v = 81.36 MeV 9337 1451 202 E_a = 385 MeV 9337 1451 203 r_v = 1.2568 fm 9337 1451 204 a_v = 0.633 fm 9337 1451 205 Surface: 9337 1451 206 W_0 = 17.2 MeV 9337 1451 207 B_s = 11.19 MeV 9337 1451 208 C_s = 0.01361 1/MeV 9337 1451 209 C_wiso = 23.5 MeV 9337 1451 210 r_s = 1.1803 fm 9337 1451 211 a_s = 0.601 fm 9337 1451 212 Spin-orbit: 9337 1451 213 V_so = 5.75 MeV 9337 1451 214 lambda_so = 0.005 1/MeV 9337 1451 215 W_so = -3.1 MeV 9337 1451 216 B_so = 160 MeV 9337 1451 217 r_so = 1.1214 fm 9337 1451 218 a_so = 0.59 fm 9337 1451 219 Coulomb: 9337 1451 220 C_coul = 1.3 9337 1451 221 r_c = 1.2452 fm 9337 1451 222 a_c = 0.545 fm 9337 1451 223 Deformation: 9337 1451 224 beta_2 = 0.213 9337 1451 225 beta_4 = 0.066 9337 1451 226 beta_6 = 0.0015 9337 1451 227 9337 1451 228 * Calculated strength function 9337 1451 229 S0= 1.04e-4 S1= 2.55e-4 R'= 9.54 fm (En=1 keV) 9337 1451 230 -------------------------------------------------- 9337 1451 231 9337 1451 232 Table 2. Level Scheme of Np-234 9337 1451 233 ------------------- 9337 1451 234 No. Ex(MeV) J PI 9337 1451 235 ------------------- 9337 1451 236 0 0.00000 0 + * 9337 1451 237 1 0.03000 2 + * 9337 1451 238 2 0.06000 1 + * 9337 1451 239 3 0.10000 4 + * 9337 1451 240 4 0.11000 3 + * 9337 1451 241 ------------------- 9337 1451 242 *) Coupled levels in CC calculation 9337 1451 243 9337 1451 244 Table 3. Level density parameters 9337 1451 245 -------------------------------------------------------- 9337 1451 246 Nuclide a* Pair Eshell T E0 Ematch 9337 1451 247 1/MeV MeV MeV MeV MeV MeV 9337 1451 248 -------------------------------------------------------- 9337 1451 249 Np-235 18.1694 0.7828 2.2924 0.3973 -0.9417 3.1303 9337 1451 250 Np-234 18.1029 0.0000 2.1332 0.2844 -0.6773 1.0000 9337 1451 251 Np-233 18.0364 0.7861 2.3620 0.4163 -1.1454 3.3864 9337 1451 252 Np-232 17.9699 0.0000 2.4351 0.2829 -0.6753 1.0000 9337 1451 253 Np-231 17.9034 0.7895 2.6707 0.2813 0.1155 1.7895 9337 1451 254 -------------------------------------------------------- 9337 1451 255 9337 1451 256 Table 4. Fission barrier parameters 9337 1451 257 ---------------------------------------- 9337 1451 258 Nuclide V_A hw_A V_B hw_B 9337 1451 259 MeV MeV MeV MeV 9337 1451 260 ---------------------------------------- 9337 1451 261 Np-235 6.250 0.950 5.630 0.600 9337 1451 262 Np-234 6.200 0.460 5.850 0.370 9337 1451 263 Np-233 4.300 0.800 3.300 0.520 9337 1451 264 Np-232 4.400 0.650 3.300 0.450 9337 1451 265 Np-231 4.000 0.800 3.100 0.520 9337 1451 266 ---------------------------------------- 9337 1451 267 9337 1451 268 Table 5. Level density above inner saddle 9337 1451 269 -------------------------------------------------------- 9337 1451 270 Nuclide a* Pair Eshell T E0 Ematch 9337 1451 271 1/MeV MeV MeV MeV MeV MeV 9337 1451 272 -------------------------------------------------------- 9337 1451 273 Np-235 20.3497 0.9133 2.6000 0.3299 -1.4981 2.9133 9337 1451 274 Np-234 20.2753 0.0000 2.6000 0.3306 -2.4114 2.0000 9337 1451 275 Np-233 20.2008 0.9172 2.6000 0.3312 -1.4942 2.9172 9337 1451 276 Np-232 20.1263 0.0000 2.6000 0.3319 -2.4114 2.0000 9337 1451 277 Np-231 20.0518 0.9211 2.6000 0.3325 -1.4903 2.9211 9337 1451 278 -------------------------------------------------------- 9337 1451 279 9337 1451 280 Table 6. Level density above outer saddle 9337 1451 281 -------------------------------------------------------- 9337 1451 282 Nuclide a* Pair Eshell T E0 Ematch 9337 1451 283 1/MeV MeV MeV MeV MeV MeV 9337 1451 284 -------------------------------------------------------- 9337 1451 285 Np-235 22.1666 0.9133 0.1600 0.3517 -0.7691 2.9133 9337 1451 286 Np-234 20.2753 0.0000 0.1200 0.3712 -1.6997 2.0000 9337 1451 287 Np-233 20.2008 0.9172 0.0800 0.3724 -0.7819 2.9172 9337 1451 288 Np-232 20.1263 0.0000 0.0400 0.3737 -1.6984 2.0000 9337 1451 289 Np-231 20.0518 0.9211 -0.0000 0.3750 -0.7767 2.9211 9337 1451 290 -------------------------------------------------------- 9337 1451 291 9337 1451 292 Table 7. Gamma-ray strength function for Np-235 9337 1451 293 -------------------------------------------------------- 9337 1451 294 K0 = 1.300 E0 = 4.500 (MeV) 9337 1451 295 * E1: ER = 10.98 (MeV) EG = 2.17 (MeV) SIG = 311.00 (mb) 9337 1451 296 ER = 14.08 (MeV) EG = 4.66 (MeV) SIG = 540.00 (mb) 9337 1451 297 * M1: ER = 6.64 (MeV) EG = 4.00 (MeV) SIG = 2.09 (mb) 9337 1451 298 * E2: ER = 10.21 (MeV) EG = 3.29 (MeV) SIG = 6.66 (mb) 9337 1451 299 -------------------------------------------------------- 9337 1451 300 9337 1451 301 9337 1451 302 References 9337 1451 303 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9337 1451 304 2) R.J.Tuttle: INDC(NDS)-107/G+Special, p.29 (1979). 9337 1451 305 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 9337 1451 306 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 9337 1451 307 5) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9337 1451 308 6) T.Ohsawa: J.Nucl. Radiochem. Sci., 9, 19 (2008). 9337 1451 309 7) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9337 1451 310 8) H.C.Britt, J.B.Wilhelmy: Nucl. Sci. Eng., 72, 222 (1979). 9337 1451 311 9) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9337 1451 312 10) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9337 1451 313 Japanese. 9337 1451 314 11) C.Kalbach: Phys. Rev. C33, 818 (1986). 9337 1451 315 12) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9337 1451 316 13) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9337 1451 317 14) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9337 1451 318 15) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9337 1451 319 16) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9337 1451 320 17) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9337 1451 321 9337 1451 322 1 451 334 19337 1451 323 2 151 4 19337 1451 324 3 4 26 19337 1451 325 3 16 13 19337 1451 326 3 17 8 19337 1451 327 3 18 116 19337 1451 328 3 102 138 19337 1451 329 8 4 2 19337 1451 330 8 16 2 19337 1451 331 8 17 2 19337 1451 332 8 18 2 19337 1451 333 8 102 2 19337 1451 334 9337 1 099999 9337 0 0 0 9.323400+4 2.320320+2 0 0 1 09337 2151 1 9.323400+4 1.000000+0 0 0 1 09337 2151 2 1.000000-5 5.000000-1 0 0 0 09337 2151 3 0.000000+0 9.539000-1 0 0 0 09337 2151 4 9337 2 099999 9337 0 0 0 9.323400+4 2.320320+2 0 0 0 09337 3 4 1 0.000000+0-3.000000+4 0 0 1 699337 3 4 2 69 2 9337 3 4 3 3.012930+4 0.000000+0 5.000000+4 8.482180-3 6.025860+4 1.630950-29337 3 4 4 7.000000+4 3.815000-2 1.000000+5 8.295210-2 1.004310+5 8.353740-29337 3 4 5 1.063630+5 9.151152-2 1.104740+5 9.703778-2 1.200000+5 1.101185-19337 3 4 6 1.400000+5 1.372676-1 1.700000+5 1.769850-1 2.000000+5 2.161847-19337 3 4 7 2.500000+5 2.766764-1 3.000000+5 3.158446-1 4.000000+5 3.903600-19337 3 4 8 5.000000+5 4.805343-1 6.000000+5 5.477380-1 7.000000+5 6.217791-19337 3 4 9 8.000000+5 6.818116-1 9.000000+5 7.435624-1 1.000000+6 8.127303-19337 3 4 10 1.100000+6 8.729066-1 1.200000+6 9.318502-1 1.300000+6 9.892842-19337 3 4 11 1.400000+6 1.044508+0 1.500000+6 1.096292+0 1.600000+6 1.145072+09337 3 4 12 1.700000+6 1.188512+0 1.800000+6 1.229000+0 1.900000+6 1.263238+09337 3 4 13 2.000000+6 1.294854+0 2.300000+6 1.362874+0 2.500000+6 1.393606+09337 3 4 14 2.700000+6 1.416086+0 3.000000+6 1.439628+0 3.500000+6 1.463497+09337 3 4 15 4.000000+6 1.475647+0 4.500000+6 1.480099+0 5.000000+6 1.481475+09337 3 4 16 5.500000+6 1.483575+0 6.000000+6 1.473994+0 6.500000+6 1.307561+09337 3 4 17 7.000000+6 1.087935+0 7.500000+6 9.149599-1 8.000000+6 7.913551-19337 3 4 18 8.500000+6 7.056665-1 9.000000+6 6.455556-1 9.500000+6 6.014824-19337 3 4 19 1.000000+7 5.673059-1 1.050000+7 5.393843-1 1.100000+7 5.157121-19337 3 4 20 1.150000+7 4.945649-1 1.200000+7 4.755498-1 1.250000+7 4.579316-19337 3 4 21 1.300000+7 4.413954-1 1.350000+7 4.257415-1 1.400000+7 4.110645-19337 3 4 22 1.450000+7 3.969500-1 1.500000+7 3.837341-1 1.550000+7 3.712840-19337 3 4 23 1.600000+7 3.591931-1 1.650000+7 3.482398-1 1.700000+7 3.374576-19337 3 4 24 1.750000+7 3.276937-1 1.800000+7 3.181028-1 1.850000+7 3.094127-19337 3 4 25 1.900000+7 3.008928-1 1.950000+7 2.931584-1 2.000000+7 2.857671-19337 3 4 26 9337 3 099999 9.323400+4 2.320320+2 0 0 0 09337 3 16 1 -6.064420+6-6.064420+6 0 0 1 299337 3 16 2 29 2 9337 3 16 3 6.090560+6 0.000000+0 6.500000+6 5.793970-3 7.000000+6 3.681630-29337 3 16 4 7.500000+6 7.894650-2 8.000000+6 1.156780-1 8.500000+6 1.412380-19337 3 16 5 9.000000+6 1.563280-1 9.500000+6 1.623520-1 1.000000+7 1.572030-19337 3 16 6 1.050000+7 1.419310-1 1.100000+7 1.199560-1 1.150000+7 1.017240-19337 3 16 7 1.200000+7 8.404010-2 1.250000+7 7.047790-2 1.300000+7 6.064150-29337 3 16 8 1.350000+7 5.389240-2 1.400000+7 4.729690-2 1.450000+7 4.452000-29337 3 16 9 1.500000+7 4.082730-2 1.550000+7 4.012970-2 1.600000+7 3.791640-29337 3 16 10 1.650000+7 3.612810-2 1.700000+7 3.467620-2 1.750000+7 3.347260-29337 3 16 11 1.800000+7 3.244920-2 1.850000+7 3.161150-2 1.900000+7 3.091640-29337 3 16 12 1.950000+7 3.037460-2 2.000000+7 2.788450-2 9337 3 16 13 9337 3 099999 9.323400+4 2.320320+2 0 0 0 09337 3 17 1 -1.354720+7-1.354720+7 0 0 1 149337 3 17 2 14 2 9337 3 17 3 1.360550+7 0.000000+0 1.400000+7 9.05390-10 1.450000+7 2.327950-79337 3 17 4 1.500000+7 1.915110-6 1.550000+7 7.796490-6 1.600000+7 2.012490-59337 3 17 5 1.650000+7 4.864270-5 1.700000+7 9.538950-5 1.750000+7 1.736710-49337 3 17 6 1.800000+7 2.774340-4 1.850000+7 3.991970-4 1.900000+7 5.189320-49337 3 17 7 1.950000+7 6.202280-4 2.000000+7 6.888720-4 9337 3 17 8 9337 3 099999 9.323400+4 2.320320+2 0 0 0 09337 3 18 1 1.923000+8 1.923000+8 0 0 1 3389337 3 18 2 338 2 9337 3 18 3 1.000000-5 1.001911+5 1.103037-5 9.539729+4 1.216691-5 9.083289+49337 3 18 4 1.342055-5 8.648693+4 1.480336-5 8.234895+4 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