JENDL-5 (Neutron sublibrary (activation cs)) Np-239 0 0 0 0 9.323900+4 2.369990+2 0 0 6 19352 1451 1 0.000000+0 1.000000+0 0 0 0 69352 1451 2 1.000000+0 2.000000+7 0 0 10 59352 1451 3 2.936000+2 0.000000+0 4 0 324 149352 1451 4 93-Np-239 JAEA+ EVAL-FEB10 O.Iwamoto,T.Nakagawa,+ 9352 1451 5 DIST-DEC21 20100304 9352 1451 6 ----JENDL-5 MATERIAL 9352 9352 1451 7 -----INCIDENT NEUTRON DATA 9352 1451 8 ------ENDF-6 FORMAT 9352 1451 9 9352 1451 10 History 9352 1451 11 07-07 New theoretical calculation was made with CCONE code. 9352 1451 12 Data were compiled as JENDL/AC-2008/1/. 9352 1451 13 10-02 Data of prompt gamma rays due to fission were given. 9352 1451 14 10-03 Covariance data were given. 9352 1451 15 21-11 revised by O.Iwamoto 9352 1451 16 (MF3/MT19-21,38) deleted 9352 1451 17 (MF8/MT4,16-18,37,102) added 9352 1451 18 9352 1451 19 9352 1451 20 MF= 1 General information 9352 1451 21 MT=452 Number of Neutrons per fission 9352 1451 22 Sum of MT's=455 and 456. 9352 1451 23 9352 1451 24 MT=455 Delayed neutron data 9352 1451 25 (same as JENDL-3.3) 9352 1451 26 Average values of systematics by Tuttle/2/, Benedetti et 9352 1451 27 al./3/ and Wald et al./4/ Decay constants were assumed to 9352 1451 28 be the same as those of Np-237 evaluated by Brady and 9352 1451 29 England/5/. 9352 1451 30 9352 1451 31 MT=456 Number of prompt neutrons per fission 9352 1451 32 Calculated with CCONE code. 9352 1451 33 9352 1451 34 MF= 2 Resonance parameters 9352 1451 35 MT=151 9352 1451 36 No resonance parameters are given. 9352 1451 37 9352 1451 38 Thermal cross sections and resonance integrals (at 300K) 9352 1451 39 ------------------------------------------------------- 9352 1451 40 0.0253 eV reson. integ.(*) 9352 1451 41 (barns) (barns) 9352 1451 42 ------------------------------------------------------- 9352 1451 43 total 56.13 9352 1451 44 elastic 11.02 9352 1451 45 fission 0.028 2.25 9352 1451 46 capture 45.02 932 9352 1451 47 ------------------------------------------------------- 9352 1451 48 (*) In the energy range from 0.5 eV to 10 MeV. 9352 1451 49 9352 1451 50 9352 1451 51 MF= 3 Neutron cross sections 9352 1451 52 Cross sections below 0.4 eV: 9352 1451 53 Assumed cross sections at 0.0253 eV: 9352 1451 54 elastic scattering 11 b from R=9.332fm calculated 9352 1451 55 with CCONE code/6/. 9352 1451 56 fission 0.028 b extrapolation of fission 9352 1451 57 cross section calculated 9352 1451 58 with CCONE code. 9352 1451 59 capture 45 b /7/ 9352 1451 60 9352 1451 61 Cross sections above 0.4 eV: 9352 1451 62 Calculated with CCONE code/6/. 9352 1451 63 9352 1451 64 MT= 1 Total cross section 9352 1451 65 The cross section was calculated with CC OMP of Soukhovitskii 9352 1451 66 et al./8/. 9352 1451 67 9352 1451 68 9352 1451 69 MF= 4 Angular distributions of secondary neutrons 9352 1451 70 MT=2 Elastic scattering 9352 1451 71 Calculated with CCONE code. 9352 1451 72 9352 1451 73 MT=18 Fission 9352 1451 74 Isotropic distributions in the laboratory system were assumed.9352 1451 75 9352 1451 76 9352 1451 77 MF= 5 Energy distributions of secondary neutrons 9352 1451 78 MT=18 Prompt neutrons 9352 1451 79 Calculated with CCONE code/6/. 9352 1451 80 9352 1451 81 9352 1451 82 MF= 6 Energy-angle distributions 9352 1451 83 Calculated with CCONE code. 9352 1451 84 Distributions from fission (MT=18) are not included. 9352 1451 85 9352 1451 86 9352 1451 87 MF=12 Photon production multiplicities 9352 1451 88 MT=18 Fission 9352 1451 89 Calculated from the total energy released by the prompt 9352 1451 90 gamma-rays due to fission which was estimated from its 9352 1451 91 systematics, and the average energy of gamma-rays. 9352 1451 92 9352 1451 93 9352 1451 94 MF=14 Photon angular distributions 9352 1451 95 MT=18 Fission 9352 1451 96 Isotoropic distributions were assumed. 9352 1451 97 9352 1451 98 9352 1451 99 MF=15 Continuous photon energy spectra 9352 1451 100 MT=18 Fission 9352 1451 101 Experimental data measured by Verbinski et al./9/ for 9352 1451 102 Pu-239 thermal fission were adopted. 9352 1451 103 9352 1451 104 9352 1451 105 MF=31 Covariances of average number of neutrons per fission 9352 1451 106 MT=452 Number of neutrons per fission 9352 1451 107 Sum of covariances for MT=455 and MT=456. 9352 1451 108 9352 1451 109 MT=455 9352 1451 110 Error of 15% was assumed. 9352 1451 111 9352 1451 112 MT=456 9352 1451 113 Covariance was obtained by fitting a linear function to the 9352 1451 114 at 0.0 and 5.0 MeV with an uncertainty of 5%. 9352 1451 115 9352 1451 116 9352 1451 117 MF=33 Covariances of neutron cross sections 9352 1451 118 Covariances were given to all the cross sections by using 9352 1451 119 KALMAN code/10/ and the covariances of model parameters 9352 1451 120 used in the cross-section calculations. 9352 1451 121 9352 1451 122 For the following cross sections, standard deviations in the 9352 1451 123 energy region below 0.4 eV were assumed as follows: 9352 1451 124 9352 1451 125 Total 41 % 9352 1451 126 Elastic scattering 50 % 9352 1451 127 Fission 50 % 9352 1451 128 Capture 50 % 9352 1451 129 9352 1451 130 9352 1451 131 MF=34 Covariances for Angular Distributions 9352 1451 132 MT=2 Elastic scattering 9352 1451 133 Covariances were given only to P1 components. 9352 1451 134 9352 1451 135 9352 1451 136 MF=35 Covariances for Energy Distributions 9352 1451 137 MT=18 Fission spectra 9352 1451 138 Estimated with CCONE and KALMAN codes. 9352 1451 139 9352 1451 140 9352 1451 141 ***************************************************************** 9352 1451 142 Calculation with CCONE code 9352 1451 143 ***************************************************************** 9352 1451 144 9352 1451 145 Models and parameters used in the CCONE/6/ calculation 9352 1451 146 1) Coupled channel optical model 9352 1451 147 Levels in the rotational band were included. Optical model 9352 1451 148 potential and coupled levels are shown in Table 1. 9352 1451 149 9352 1451 150 2) Two-component exciton model/11/ 9352 1451 151 * Global parametrization of Koning-Duijvestijn/12/ 9352 1451 152 was used. 9352 1451 153 * Gamma emission channel/13/ was added to simulate direct 9352 1451 154 and semi-direct capture reaction. 9352 1451 155 9352 1451 156 3) Hauser-Feshbach statistical model 9352 1451 157 * Moldauer width fluctuation correction/14/ was included. 9352 1451 158 * Neutron, gamma and fission decay channel were included. 9352 1451 159 * Transmission coefficients of neutrons were taken from 9352 1451 160 coupled channel calculation in Table 1. 9352 1451 161 * The level scheme of the target is shown in Table 2. 9352 1451 162 * Level density formula of constant temperature and Fermi-gas 9352 1451 163 model were used with shell energy correction and collective 9352 1451 164 enhancement factor. Parameters are shown in Table 3. 9352 1451 165 * Fission channel: 9352 1451 166 Double humped fission barriers were assumed. 9352 1451 167 Fission barrier penetrabilities were calculated with 9352 1451 168 Hill-Wheler formula/15/. Fission barrier parameters were 9352 1451 169 shown in Table 4. Transition state model was used and 9352 1451 170 continuum levels are assumed above the saddles. The level 9352 1451 171 density parameters for inner and outer saddles are shown in 9352 1451 172 Tables 5 and 6, respectively. 9352 1451 173 * Gamma-ray strength function of Kopecky et al/16/,/17/ 9352 1451 174 was used. The prameters are shown in Table 7. 9352 1451 175 9352 1451 176 9352 1451 177 ------------------------------------------------------------------9352 1451 178 Tables 9352 1451 179 ------------------------------------------------------------------9352 1451 180 9352 1451 181 Table 1. Coupled channel calculation 9352 1451 182 -------------------------------------------------- 9352 1451 183 * rigid rotor model was applied 9352 1451 184 * coupled levels = 0,1,2,5,7 (see Table 2) 9352 1451 185 * optical potential parameters /8/ 9352 1451 186 Volume: 9352 1451 187 V_0 = 49.97 MeV 9352 1451 188 lambda_HF = 0.01004 1/MeV 9352 1451 189 C_viso = 15.9 MeV 9352 1451 190 A_v = 12.04 MeV 9352 1451 191 B_v = 81.36 MeV 9352 1451 192 E_a = 385 MeV 9352 1451 193 r_v = 1.2568 fm 9352 1451 194 a_v = 0.633 fm 9352 1451 195 Surface: 9352 1451 196 W_0 = 17.2 MeV 9352 1451 197 B_s = 11.19 MeV 9352 1451 198 C_s = 0.01361 1/MeV 9352 1451 199 C_wiso = 23.5 MeV 9352 1451 200 r_s = 1.1803 fm 9352 1451 201 a_s = 0.601 fm 9352 1451 202 Spin-orbit: 9352 1451 203 V_so = 5.75 MeV 9352 1451 204 lambda_so = 0.005 1/MeV 9352 1451 205 W_so = -3.1 MeV 9352 1451 206 B_so = 160 MeV 9352 1451 207 r_so = 1.1214 fm 9352 1451 208 a_so = 0.59 fm 9352 1451 209 Coulomb: 9352 1451 210 C_coul = 1.3 9352 1451 211 r_c = 1.2452 fm 9352 1451 212 a_c = 0.545 fm 9352 1451 213 Deformation: 9352 1451 214 beta_2 = 0.213 9352 1451 215 beta_4 = 0.066 9352 1451 216 beta_6 = 0.0015 9352 1451 217 9352 1451 218 * Calculated strength function 9352 1451 219 S0= 0.86e-4 S1= 3.09e-4 R'= 9.33 fm (En=1 keV) 9352 1451 220 -------------------------------------------------- 9352 1451 221 9352 1451 222 Table 2. Level Scheme of Np-239 9352 1451 223 ------------------- 9352 1451 224 No. Ex(MeV) J PI 9352 1451 225 ------------------- 9352 1451 226 0 0.00000 5/2 + * 9352 1451 227 1 0.03113 7/2 + * 9352 1451 228 2 0.07121 9/2 + * 9352 1451 229 3 0.07466 5/2 - 9352 1451 230 4 0.11784 7/2 - 9352 1451 231 5 0.12250 11/2 + * 9352 1451 232 6 0.17302 9/2 - 9352 1451 233 7 0.18000 13/2 + * 9352 1451 234 8 0.22020 1/2 + 9352 1451 235 9 0.24136 11/2 - 9352 1451 236 10 0.25830 3/2 + 9352 1451 237 11 0.26080 3/2 - 9352 1451 238 12 0.26700 7/2 + 9352 1451 239 13 0.27090 1/2 - 9352 1451 240 14 0.31550 7/2 - 9352 1451 241 15 0.31740 13/2 - 9352 1451 242 16 0.32500 5/2 - 9352 1451 243 17 0.34700 9/2 + 9352 1451 244 18 0.35900 9/2 + 9352 1451 245 19 0.41100 13/2 - 9352 1451 246 20 0.42060 11/2 - 9352 1451 247 ------------------- 9352 1451 248 *) Coupled levels in CC calculation 9352 1451 249 9352 1451 250 Table 3. Level density parameters 9352 1451 251 -------------------------------------------------------- 9352 1451 252 Nuclide a* Pair Eshell T E0 Ematch 9352 1451 253 1/MeV MeV MeV MeV MeV MeV 9352 1451 254 -------------------------------------------------------- 9352 1451 255 Np-240 18.5012 0.0000 2.6950 0.2755 -0.6794 1.0000 9352 1451 256 Np-239 18.4349 0.7762 2.6850 0.3834 -0.8836 3.0329 9352 1451 257 Np-238 18.3685 0.0000 2.2742 0.3205 -0.9882 1.4160 9352 1451 258 Np-237 18.3022 0.7795 2.4371 0.3963 -0.9739 3.1569 9352 1451 259 Np-236 18.2358 0.0000 2.1332 0.2999 -0.7994 1.1664 9352 1451 260 -------------------------------------------------------- 9352 1451 261 9352 1451 262 Table 4. Fission barrier parameters 9352 1451 263 ---------------------------------------- 9352 1451 264 Nuclide V_A hw_A V_B hw_B 9352 1451 265 MeV MeV MeV MeV 9352 1451 266 ---------------------------------------- 9352 1451 267 Np-240 6.200 0.460 5.850 0.370 9352 1451 268 Np-239 6.250 0.800 5.200 0.600 9352 1451 269 Np-238 6.200 0.460 5.850 0.370 9352 1451 270 Np-237 6.250 0.950 5.200 0.600 9352 1451 271 Np-236 6.200 0.600 5.850 0.400 9352 1451 272 ---------------------------------------- 9352 1451 273 9352 1451 274 Table 5. Level density above inner saddle 9352 1451 275 -------------------------------------------------------- 9352 1451 276 Nuclide a* Pair Eshell T E0 Ematch 9352 1451 277 1/MeV MeV MeV MeV MeV MeV 9352 1451 278 -------------------------------------------------------- 9352 1451 279 Np-240 20.7213 0.0000 2.6000 0.3267 -2.4114 2.0000 9352 1451 280 Np-239 20.6471 0.9056 2.6000 0.3273 -1.5058 2.9056 9352 1451 281 Np-238 20.5728 0.0000 2.6000 0.3280 -2.4114 2.0000 9352 1451 282 Np-237 20.4984 0.9094 2.6000 0.3286 -1.5020 2.9094 9352 1451 283 Np-236 20.4241 0.0000 2.6000 0.3293 -2.4114 2.0000 9352 1451 284 -------------------------------------------------------- 9352 1451 285 9352 1451 286 Table 6. Level density above outer saddle 9352 1451 287 -------------------------------------------------------- 9352 1451 288 Nuclide a* Pair Eshell T E0 Ematch 9352 1451 289 1/MeV MeV MeV MeV MeV MeV 9352 1451 290 -------------------------------------------------------- 9352 1451 291 Np-240 20.7213 0.0000 0.3600 0.3637 -1.7033 2.0000 9352 1451 292 Np-239 20.6471 0.9056 0.3200 0.3649 -0.7971 2.9056 9352 1451 293 Np-238 20.5728 0.0000 0.2800 0.3661 -1.7021 2.0000 9352 1451 294 Np-237 20.4984 0.9094 0.2400 0.3674 -0.7921 2.9094 9352 1451 295 Np-236 20.4241 0.0000 0.2000 0.3686 -1.7009 2.0000 9352 1451 296 -------------------------------------------------------- 9352 1451 297 9352 1451 298 Table 7. Gamma-ray strength function for Np-240 9352 1451 299 -------------------------------------------------------- 9352 1451 300 K0 = 1.300 E0 = 4.500 (MeV) 9352 1451 301 * E1: ER = 10.98 (MeV) EG = 2.17 (MeV) SIG = 311.00 (mb) 9352 1451 302 ER = 14.08 (MeV) EG = 4.66 (MeV) SIG = 540.00 (mb) 9352 1451 303 * M1: ER = 6.60 (MeV) EG = 4.00 (MeV) SIG = 2.07 (mb) 9352 1451 304 * E2: ER = 10.14 (MeV) EG = 3.23 (MeV) SIG = 6.64 (mb) 9352 1451 305 -------------------------------------------------------- 9352 1451 306 9352 1451 307 9352 1451 308 References 9352 1451 309 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9352 1451 310 2) R.J.Tuttle: INDC(NDS)-107/G+Special, p.29 (1979). 9352 1451 311 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 9352 1451 312 4) R.Waldo et al.: Phys. Rrev., C23, 1113 (1981). 9352 1451 313 5) M.C.Brady, T.R.England: Nucl. Sci. Eng., 103, 129 (1989). 9352 1451 314 6) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9352 1451 315 7) R.W.Stoughton, J.Halperin: Nucl. Sci. Eng., 6, 100 (1959). 9352 1451 316 8) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9352 1451 317 9) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9352 1451 318 10) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9352 1451 319 Japanese. 9352 1451 320 11) C.Kalbach: Phys. Rev. C33, 818 (1986). 9352 1451 321 12) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9352 1451 322 13) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9352 1451 323 14) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9352 1451 324 15) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9352 1451 325 16) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9352 1451 326 17) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9352 1451 327 9352 1451 328 1 451 342 19352 1451 329 2 151 4 19352 1451 330 3 4 32 19352 1451 331 3 16 13 19352 1451 332 3 17 9 19352 1451 333 3 18 153 19352 1451 334 3 37 5 19352 1451 335 3 102 173 19352 1451 336 8 4 2 19352 1451 337 8 16 2 19352 1451 338 8 17 2 19352 1451 339 8 18 2 19352 1451 340 8 37 2 19352 1451 341 8 102 2 19352 1451 342 9352 1 099999 9352 0 0 0 9.323900+4 2.369990+2 0 0 1 09352 2151 1 9.323900+4 1.000000+0 0 0 1 09352 2151 2 1.000000-5 4.000000-1 0 0 0 09352 2151 3 2.500000+0 9.332000-1 0 0 0 09352 2151 4 9352 2 099999 9352 0 0 0 9.323900+4 2.369990+2 0 0 0 09352 3 4 1 0.000000+0-3.113100+4 0 0 1 869352 3 4 2 86 2 9352 3 4 3 3.126240+4 0.000000+0 5.000000+4 2.596410-1 7.000000+4 4.096600-19352 3 4 4 7.151050+4 4.188100-1 7.497900+4 4.462296-1 1.000000+5 8.497912-19352 3 4 5 1.100920+5 9.274258-1 1.183370+5 9.908759-1 1.200000+5 1.027471+09352 3 4 6 1.230170+5 1.062955+0 1.400000+5 1.209414+0 1.700000+5 1.397443+09352 3 4 7 1.737500+5 1.418139+0 1.807590+5 1.465162+0 1.807600+5 1.465168+09352 3 4 8 2.000000+5 1.573240+0 2.211290+5 1.628921+0 2.423780+5 1.699662+09352 3 4 9 2.500000+5 1.725058+0 2.593900+5 1.756418+0 2.618990+5 1.770379+09352 3 4 10 2.681270+5 1.818953+0 2.720430+5 1.846332+0 3.000000+5 2.019885+09352 3 4 11 3.168310+5 2.069766+0 3.187390+5 2.080026+0 3.263710+5 2.105911+09352 3 4 12 3.484640+5 2.186564+0 3.605150+5 2.222739+0 4.000000+5 2.330298+09352 3 4 13 4.127340+5 2.363115+0 4.223750+5 2.387563+0 5.000000+5 2.580035+09352 3 4 14 6.000000+5 2.673610+0 7.000000+5 2.821263+0 8.000000+5 2.883768+09352 3 4 15 9.000000+5 2.912428+0 1.000000+6 2.892319+0 1.100000+6 2.814780+09352 3 4 16 1.200000+6 2.761709+0 1.300000+6 2.744340+0 1.400000+6 2.751595+09352 3 4 17 1.500000+6 2.763981+0 1.600000+6 2.783897+0 1.700000+6 2.795890+09352 3 4 18 1.800000+6 2.810561+0 1.900000+6 2.813517+0 2.000000+6 2.817896+09352 3 4 19 2.300000+6 2.792632+0 2.500000+6 2.760922+0 2.700000+6 2.724275+09352 3 4 20 3.000000+6 2.664633+0 3.500000+6 2.593375+0 4.000000+6 2.544566+09352 3 4 21 4.500000+6 2.516378+0 5.000000+6 2.505027+0 5.500000+6 2.483132+09352 3 4 22 6.000000+6 2.344287+0 6.500000+6 1.913790+0 7.000000+6 1.454247+09352 3 4 23 7.500000+6 1.099182+0 8.000000+6 8.656663-1 8.500000+6 7.127010-19352 3 4 24 9.000000+6 6.175770-1 9.500000+6 5.540765-1 1.000000+7 5.108204-19352 3 4 25 1.050000+7 4.785924-1 1.100000+7 4.530977-1 1.150000+7 4.320605-19352 3 4 26 1.200000+7 4.130346-1 1.250000+7 3.962793-1 1.300000+7 3.803511-19352 3 4 27 1.350000+7 3.658354-1 1.400000+7 3.519278-1 1.450000+7 3.389942-19352 3 4 28 1.500000+7 3.265487-1 1.550000+7 3.150063-1 1.600000+7 3.039329-19352 3 4 29 1.650000+7 2.939683-1 1.700000+7 2.838956-1 1.750000+7 2.750364-19352 3 4 30 1.800000+7 2.663529-1 1.850000+7 2.584916-1 1.900000+7 2.507910-19352 3 4 31 1.950000+7 2.440182-1 2.000000+7 2.371648-1 9352 3 4 32 9352 3 099999 9.323900+4 2.369990+2 0 0 0 09352 3 16 1 -6.215200+6-6.215200+6 0 0 1 299352 3 16 2 29 2 9352 3 16 3 6.241430+6 0.000000+0 6.500000+6 6.906650-3 7.000000+6 1.503600-19352 3 16 4 7.500000+6 4.143240-1 8.000000+6 6.793600-1 8.500000+6 8.931720-19352 3 16 5 9.000000+6 1.054530+0 9.500000+6 1.162510+0 1.000000+7 1.236050+09352 3 16 6 1.050000+7 1.281590+0 1.100000+7 1.316460+0 1.150000+7 1.339200+09352 3 16 7 1.200000+7 1.362670+0 1.250000+7 1.371130+0 1.300000+7 1.332030+09352 3 16 8 1.350000+7 1.239800+0 1.400000+7 1.101620+0 1.450000+7 9.563140-19352 3 16 9 1.500000+7 8.155440-1 1.550000+7 6.944500-1 1.600000+7 5.927650-19352 3 16 10 1.650000+7 5.091250-1 1.700000+7 4.506050-1 1.750000+7 4.026350-19352 3 16 11 1.800000+7 3.654000-1 1.850000+7 3.369550-1 1.900000+7 3.163330-19352 3 16 12 1.950000+7 2.941670-1 2.000000+7 2.797300-1 9352 3 16 13 9352 3 099999 9.323900+4 2.369990+2 0 0 0 09352 3 17 1 -1.170350+7-1.170350+7 0 0 1 189352 3 17 2 18 2 9352 3 17 3 1.175290+7 0.000000+0 1.200000+7 1.585840-5 1.250000+7 8.433150-39352 3 17 4 1.300000+7 4.843170-2 1.350000+7 1.090400-1 1.400000+7 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