JENDL-5 (Neutron sublibrary (activation cs)) Np-235 0 0 0 0 9.323500+4 2.330250+2 0 0 6 19340 1451 1 0.000000+0 1.000000+0 0 0 0 69340 1451 2 1.000000+0 2.000000+7 0 0 10 59340 1451 3 2.936000+2 0.000000+0 4 0 318 129340 1451 4 93-Np-235 JAEA+ EVAL-FEB10 O.Iwamoto,T.Nakagawa,+ 9340 1451 5 DIST-DEC21 20100304 9340 1451 6 ----JENDL-5 MATERIAL 9340 9340 1451 7 -----INCIDENT NEUTRON DATA 9340 1451 8 ------ENDF-6 FORMAT 9340 1451 9 9340 1451 10 History 9340 1451 11 07-07 New theoretical calculation was made with CCONE code. 9340 1451 12 07-10 Theoretical calculation was made with CCONE code. 9340 1451 13 Data were compiled as JENDL/AC-2008/1/. 9340 1451 14 09-02 (3,102) below 0.2 eV, (1,452), (1,455) and (1,456) were 9340 1451 15 revised. 9340 1451 16 10-02 Data of prompt gamma rays due to fission were given. 9340 1451 17 10-03 Covariance data were given. 9340 1451 18 9340 1451 19 21-11 revised by O.Iwamoto 9340 1451 20 (MF3/MT19-21,38) deleted 9340 1451 21 (MF8/MT4,16-18,102) added 9340 1451 22 9340 1451 23 MF= 1 General information 9340 1451 24 MT=452 Number of Neutrons per fission 9340 1451 25 Sum of MT's=455 and 456. 9340 1451 26 9340 1451 27 MT=455 Delayed neutron data 9340 1451 28 Estimated from systematics by Tuttle/2/, Benedetti et al./3/ 9340 1451 29 and Waldo et al./4/, and partial fission cross sections 9340 1451 30 calculated with CCONE code/5/. 9340 1451 31 9340 1451 32 MT=456 Number of prompt neutrons per fission 9340 1451 33 Ohsawa's systematics /6/ was adopted. 9340 1451 34 9340 1451 35 MF= 2 Resonance parameters 9340 1451 36 MT=151 9340 1451 37 No resonance parameters are given. 9340 1451 38 9340 1451 39 Thermal cross sections and resonance integrals (at 300K) 9340 1451 40 ------------------------------------------------------- 9340 1451 41 0.0253 eV reson. integ.(*) 9340 1451 42 (barns) (barns) 9340 1451 43 ------------------------------------------------------- 9340 1451 44 total 219.53 9340 1451 45 elastic 11.32 9340 1451 46 fission 53.02 303 9340 1451 47 capture 155.06 814 9340 1451 48 ------------------------------------------------------- 9340 1451 49 (*) In the energy range from 0.5 eV to 10 MeV. 9340 1451 50 9340 1451 51 9340 1451 52 MF= 3 Neutron cross sections 9340 1451 53 Cross sections below 0.2 eV: 9340 1451 54 Assumed thermal cross sections: 9340 1451 55 elastic scattering 11.3 b from R=9.484fm calculated 9340 1451 56 with CCONE code/5/. 9340 1451 57 fission 53 b from CCONE calculation and 9340 1451 58 capture cross section 9340 1451 59 capture 155 b /7/. The capture cross 9340 1451 60 section of Np237 was assumed 9340 1451 61 to be 178 b. 9340 1451 62 9340 1451 63 Cross sections above 0.2 eV: 9340 1451 64 Calculated with CCONE code /5/. 9340 1451 65 9340 1451 66 MT= 1 Total cross section 9340 1451 67 The cross section was calculated with CC OMP of Soukhovitskii 9340 1451 68 et al./8/. 9340 1451 69 9340 1451 70 MT=18 Fission cross section 9340 1451 71 Calculated with CCONE code. The simulated (n,f) cross section 9340 1451 72 of Britt and Wilhelmy/9/ was used to determine the parameters 9340 1451 73 in the CCONE calculation. 9340 1451 74 9340 1451 75 9340 1451 76 MF= 4 Angular distributions of secondary neutrons 9340 1451 77 MT=2 Elastic scattering 9340 1451 78 Calculated with CCONE code. 9340 1451 79 9340 1451 80 MT=18 Fission 9340 1451 81 Isotropic distributions in the laboratory system were assumed.9340 1451 82 9340 1451 83 9340 1451 84 MF= 5 Energy distributions of secondary neutrons 9340 1451 85 MT=18 Prompt neutrons 9340 1451 86 Calculated with CCONE code/5/. 9340 1451 87 9340 1451 88 9340 1451 89 MF= 6 Energy-angle distributions 9340 1451 90 Calculated with CCONE code. 9340 1451 91 Distributions from fission (MT=18) are not included. 9340 1451 92 9340 1451 93 9340 1451 94 MF=12 Photon production multiplicities 9340 1451 95 MT=18 Fission 9340 1451 96 Calculated from the total energy released by the prompt 9340 1451 97 gamma-rays due to fission which was estimated from its 9340 1451 98 systematics, and the average energy of gamma-rays. 9340 1451 99 9340 1451 100 9340 1451 101 MF=14 Photon angular distributions 9340 1451 102 MT=18 Fission 9340 1451 103 Isotoropic distributions were assumed. 9340 1451 104 9340 1451 105 9340 1451 106 MF=15 Continuous photon energy spectra 9340 1451 107 MT=18 Fission 9340 1451 108 Experimental data measured by Verbinski et al./10/ for 9340 1451 109 Pu-239 thermal fission were adopted. 9340 1451 110 9340 1451 111 9340 1451 112 MF=31 Covariances of average number of neutrons per fission 9340 1451 113 MT=452 Number of neutrons per fission 9340 1451 114 Sum of covariances for MT=455 and MT=456. 9340 1451 115 9340 1451 116 MT=455 9340 1451 117 Error of 15% was assumed. 9340 1451 118 9340 1451 119 MT=456 9340 1451 120 Covariance was obtained by fitting a linear function to the 9340 1451 121 at 0.0 and 5.0 MeV with an uncertainty of 5%. 9340 1451 122 9340 1451 123 9340 1451 124 MF=33 Covariances of neutron cross sections 9340 1451 125 Covariances were given to all the cross sections by using 9340 1451 126 KALMAN code/11/ and the covariances of model parameters 9340 1451 127 used in the cross-section calculations. 9340 1451 128 9340 1451 129 Covariances of the fission cross section were determined from 9340 1451 130 experimental data. 9340 1451 131 9340 1451 132 For the following cross sections, standard deviations in the 9340 1451 133 energy region below 0.2 eV were assumed as follows: 9340 1451 134 9340 1451 135 Total 12 % 9340 1451 136 Elastic scattering 50 % 9340 1451 137 Fission 50 % 9340 1451 138 Capture 1.8 % estimated from experimental data. 9340 1451 139 9340 1451 140 9340 1451 141 MF=34 Covariances for Angular Distributions 9340 1451 142 MT=2 Elastic scattering 9340 1451 143 Covariances were given only to P1 components. 9340 1451 144 9340 1451 145 9340 1451 146 MF=35 Covariances for Energy Distributions 9340 1451 147 MT=18 Fission spectra 9340 1451 148 Estimated with CCONE and KALMAN codes. 9340 1451 149 9340 1451 150 9340 1451 151 ***************************************************************** 9340 1451 152 Calculation with CCONE code 9340 1451 153 ***************************************************************** 9340 1451 154 9340 1451 155 Models and parameters used in the CCONE/5/ calculation 9340 1451 156 1) Coupled channel optical model 9340 1451 157 Levels in the rotational band were included. Optical model 9340 1451 158 potential and coupled levels are shown in Table 1. 9340 1451 159 9340 1451 160 2) Two-component exciton model/12/ 9340 1451 161 * Global parametrization of Koning-Duijvestijn/13/ 9340 1451 162 was used. 9340 1451 163 * Gamma emission channel/14/ was added to simulate direct 9340 1451 164 and semi-direct capture reaction. 9340 1451 165 9340 1451 166 3) Hauser-Feshbach statistical model 9340 1451 167 * Moldauer width fluctuation correction/15/ was included. 9340 1451 168 * Neutron, gamma and fission decay channel were included. 9340 1451 169 * Transmission coefficients of neutrons were taken from 9340 1451 170 coupled channel calculation in Table 1. 9340 1451 171 * The level scheme of the target is shown in Table 2. 9340 1451 172 * Level density formula of constant temperature and Fermi-gas 9340 1451 173 model were used with shell energy correction and collective 9340 1451 174 enhancement factor. Parameters are shown in Table 3. 9340 1451 175 * Fission channel: 9340 1451 176 Double humped fission barriers were assumed. 9340 1451 177 Fission barrier penetrabilities were calculated with 9340 1451 178 Hill-Wheler formula/16/. Fission barrier parameters were 9340 1451 179 shown in Table 4. Transition state model was used and 9340 1451 180 continuum levels are assumed above the saddles. The level 9340 1451 181 density parameters for inner and outer saddles are shown in 9340 1451 182 Tables 5 and 6, respectively. 9340 1451 183 * Gamma-ray strength function of Kopecky et al/17/,/18/ 9340 1451 184 was used. The prameters are shown in Table 7. 9340 1451 185 9340 1451 186 9340 1451 187 ------------------------------------------------------------------9340 1451 188 Tables 9340 1451 189 ------------------------------------------------------------------9340 1451 190 9340 1451 191 Table 1. Coupled channel calculation 9340 1451 192 -------------------------------------------------- 9340 1451 193 * rigid rotor model was applied 9340 1451 194 * coupled levels = 0,1,3,5,7 (see Table 2) 9340 1451 195 * optical potential parameters /8/ 9340 1451 196 Volume: 9340 1451 197 V_0 = 49.97 MeV 9340 1451 198 lambda_HF = 0.01004 1/MeV 9340 1451 199 C_viso = 15.9 MeV 9340 1451 200 A_v = 12.04 MeV 9340 1451 201 B_v = 81.36 MeV 9340 1451 202 E_a = 385 MeV 9340 1451 203 r_v = 1.2568 fm 9340 1451 204 a_v = 0.633 fm 9340 1451 205 Surface: 9340 1451 206 W_0 = 17.2 MeV 9340 1451 207 B_s = 11.19 MeV 9340 1451 208 C_s = 0.01361 1/MeV 9340 1451 209 C_wiso = 23.5 MeV 9340 1451 210 r_s = 1.1803 fm 9340 1451 211 a_s = 0.601 fm 9340 1451 212 Spin-orbit: 9340 1451 213 V_so = 5.75 MeV 9340 1451 214 lambda_so = 0.005 1/MeV 9340 1451 215 W_so = -3.1 MeV 9340 1451 216 B_so = 160 MeV 9340 1451 217 r_so = 1.1214 fm 9340 1451 218 a_so = 0.59 fm 9340 1451 219 Coulomb: 9340 1451 220 C_coul = 1.3 9340 1451 221 r_c = 1.2452 fm 9340 1451 222 a_c = 0.545 fm 9340 1451 223 Deformation: 9340 1451 224 beta_2 = 0.213 9340 1451 225 beta_4 = 0.066 9340 1451 226 beta_6 = 0.0015 9340 1451 227 9340 1451 228 * Calculated strength function 9340 1451 229 S0= 0.98e-4 S1= 3.08e-4 R'= 9.48 fm (En=1 keV) 9340 1451 230 -------------------------------------------------- 9340 1451 231 9340 1451 232 Table 2. Level Scheme of Np-235 9340 1451 233 ------------------- 9340 1451 234 No. Ex(MeV) J PI 9340 1451 235 ------------------- 9340 1451 236 0 0.00000 5/2 + * 9340 1451 237 1 0.03423 7/2 + * 9340 1451 238 2 0.04910 5/2 - 9340 1451 239 3 0.07910 9/2 + * 9340 1451 240 4 0.09160 7/2 - 9340 1451 241 5 0.13300 11/2 + * 9340 1451 242 6 0.14680 9/2 - 9340 1451 243 7 0.20000 13/2 + * 9340 1451 244 ------------------- 9340 1451 245 *) Coupled levels in CC calculation 9340 1451 246 9340 1451 247 Table 3. Level density parameters 9340 1451 248 -------------------------------------------------------- 9340 1451 249 Nuclide a* Pair Eshell T E0 Ematch 9340 1451 250 1/MeV MeV MeV MeV MeV MeV 9340 1451 251 -------------------------------------------------------- 9340 1451 252 Np-236 18.2358 0.0000 2.1332 0.2999 -0.7994 1.1664 9340 1451 253 Np-235 18.1694 0.7828 2.2924 0.3973 -0.9417 3.1303 9340 1451 254 Np-234 18.1029 0.0000 2.1332 0.2844 -0.6773 1.0000 9340 1451 255 Np-233 18.0364 0.7861 2.3620 0.4163 -1.1454 3.3864 9340 1451 256 -------------------------------------------------------- 9340 1451 257 9340 1451 258 Table 4. Fission barrier parameters 9340 1451 259 ---------------------------------------- 9340 1451 260 Nuclide V_A hw_A V_B hw_B 9340 1451 261 MeV MeV MeV MeV 9340 1451 262 ---------------------------------------- 9340 1451 263 Np-236 6.100 0.600 6.080 0.600 9340 1451 264 Np-235 6.250 0.950 5.630 0.600 9340 1451 265 Np-234 6.200 0.460 5.850 0.370 9340 1451 266 Np-233 4.300 0.800 3.300 0.520 9340 1451 267 ---------------------------------------- 9340 1451 268 9340 1451 269 Table 5. Level density above inner saddle 9340 1451 270 -------------------------------------------------------- 9340 1451 271 Nuclide a* Pair Eshell T E0 Ematch 9340 1451 272 1/MeV MeV MeV MeV MeV MeV 9340 1451 273 -------------------------------------------------------- 9340 1451 274 Np-236 22.2477 0.0000 2.6000 0.3139 -2.3586 2.0000 9340 1451 275 Np-235 20.3497 0.9133 2.6000 0.3299 -1.4981 2.9133 9340 1451 276 Np-234 20.2753 0.0000 2.6000 0.3306 -2.4114 2.0000 9340 1451 277 Np-233 20.2008 0.9172 2.6000 0.3312 -1.4942 2.9172 9340 1451 278 -------------------------------------------------------- 9340 1451 279 9340 1451 280 Table 6. Level density above outer saddle 9340 1451 281 -------------------------------------------------------- 9340 1451 282 Nuclide a* Pair Eshell T E0 Ematch 9340 1451 283 1/MeV MeV MeV MeV MeV MeV 9340 1451 284 -------------------------------------------------------- 9340 1451 285 Np-236 22.2477 0.0000 0.2000 0.3977 -2.2734 2.7000 9340 1451 286 Np-235 22.1666 0.9133 0.1600 0.3517 -0.7691 2.9133 9340 1451 287 Np-234 20.2753 0.0000 0.1200 0.3712 -1.6997 2.0000 9340 1451 288 Np-233 20.2008 0.9172 0.0800 0.3724 -0.7819 2.9172 9340 1451 289 -------------------------------------------------------- 9340 1451 290 9340 1451 291 Table 7. Gamma-ray strength function for Np-236 9340 1451 292 -------------------------------------------------------- 9340 1451 293 K0 = 1.300 E0 = 4.500 (MeV) 9340 1451 294 * E1: ER = 10.98 (MeV) EG = 2.17 (MeV) SIG = 311.00 (mb) 9340 1451 295 ER = 14.08 (MeV) EG = 4.66 (MeV) SIG = 540.00 (mb) 9340 1451 296 * M1: ER = 6.63 (MeV) EG = 4.00 (MeV) SIG = 2.09 (mb) 9340 1451 297 * E2: ER = 10.19 (MeV) EG = 3.28 (MeV) SIG = 6.66 (mb) 9340 1451 298 -------------------------------------------------------- 9340 1451 299 9340 1451 300 9340 1451 301 References 9340 1451 302 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9340 1451 303 2) R.J.Tuttle: INDC(NDS)-107/G+Special, p.29 (1979). 9340 1451 304 3) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982). 9340 1451 305 4) R.Waldo et al.: Phys. Rev., C23, 1113 (1981). 9340 1451 306 5) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9340 1451 307 6) T.Ohsawa: J.Nucl. Radiochem. Sci., 9, 19 (2008). 9340 1451 308 7) J.H.Landrum et al.: UCRL-51263 (1972). 9340 1451 309 8) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9340 1451 310 9) H.C.Britt, J.B.Wilhelmy: Nucl. Sci. Eng., 72, 222 (1979). 9340 1451 311 10) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9340 1451 312 11) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9340 1451 313 Japanese. 9340 1451 314 12) C.Kalbach: Phys. Rev. C33, 818 (1986). 9340 1451 315 13) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9340 1451 316 14) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9340 1451 317 15) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9340 1451 318 16) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9340 1451 319 17) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9340 1451 320 18) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9340 1451 321 9340 1451 322 1 451 334 19340 1451 323 2 151 4 19340 1451 324 3 4 27 19340 1451 325 3 16 12 19340 1451 326 3 17 8 19340 1451 327 3 18 128 19340 1451 328 3 102 163 19340 1451 329 8 4 2 19340 1451 330 8 16 2 19340 1451 331 8 17 2 19340 1451 332 8 18 2 19340 1451 333 8 102 2 19340 1451 334 9340 1 099999 9340 0 0 0 9.323500+4 2.330250+2 0 0 1 09340 2151 1 9.323500+4 1.000000+0 0 0 1 09340 2151 2 1.000000-5 2.000000-1 0 0 0 09340 2151 3 2.500000+0 9.484000-1 0 0 0 09340 2151 4 9340 2 099999 9340 0 0 0 9.323500+4 2.330250+2 0 0 0 09340 3 4 1 0.000000+0-3.423000+4 0 0 1 729340 3 4 2 72 2 9340 3 4 3 3.437690+4 0.000000+0 4.931070+4 1.063060-1 5.000000+4 1.365194-19340 3 4 4 7.000000+4 3.349820-1 7.943940+4 3.955810-1 9.199310+4 4.754753-19340 3 4 5 1.000000+5 5.734742-1 1.109460+5 6.360684-1 1.200000+5 6.878516-19340 3 4 6 1.335710+5 7.440327-1 1.400000+5 7.672935-1 1.474300+5 7.917037-19340 3 4 7 1.700000+5 8.707644-1 2.000000+5 9.420566-1 2.008580+5 9.422344-19340 3 4 8 2.500000+5 9.393254-1 3.000000+5 9.153863-1 4.000000+5 8.105716-19340 3 4 9 5.000000+5 8.081557-1 6.000000+5 8.048173-1 7.000000+5 8.346759-19340 3 4 10 8.000000+5 8.590592-1 9.000000+5 8.934888-1 1.000000+6 9.389265-19340 3 4 11 1.100000+6 9.779085-1 1.200000+6 1.016254+0 1.300000+6 1.053316+09340 3 4 12 1.400000+6 1.089873+0 1.500000+6 1.122959+0 1.600000+6 1.154620+09340 3 4 13 1.700000+6 1.181042+0 1.800000+6 1.206013+0 1.900000+6 1.225071+09340 3 4 14 2.000000+6 1.242824+0 2.300000+6 1.274132+0 2.500000+6 1.282853+09340 3 4 15 2.700000+6 1.287164+0 3.000000+6 1.287660+0 3.500000+6 1.285989+09340 3 4 16 4.000000+6 1.291896+0 4.500000+6 1.302238+0 5.000000+6 1.316814+09340 3 4 17 5.500000+6 1.317368+0 6.000000+6 1.227781+0 6.500000+6 1.039623+09340 3 4 18 7.000000+6 8.647338-1 7.500000+6 7.294634-1 8.000000+6 6.351200-19340 3 4 19 8.500000+6 5.659889-1 9.000000+6 5.176012-1 9.500000+6 4.807131-19340 3 4 20 1.000000+7 4.526388-1 1.050000+7 4.296524-1 1.100000+7 4.103267-19340 3 4 21 1.150000+7 3.934621-1 1.200000+7 3.779438-1 1.250000+7 3.638343-19340 3 4 22 1.300000+7 3.502388-1 1.350000+7 3.377434-1 1.400000+7 3.254981-19340 3 4 23 1.450000+7 3.142403-1 1.500000+7 3.031346-1 1.550000+7 2.930567-19340 3 4 24 1.600000+7 2.830980-1 1.650000+7 2.740993-1 1.700000+7 2.652719-19340 3 4 25 1.750000+7 2.572330-1 1.800000+7 2.493882-1 1.850000+7 2.422695-19340 3 4 26 1.900000+7 2.353051-1 1.950000+7 2.289616-1 2.000000+7 2.227652-19340 3 4 27 9340 3 099999 9.323500+4 2.330250+2 0 0 0 09340 3 16 1 -6.983120+6-6.983120+6 0 0 1 279340 3 16 2 27 2 9340 3 16 3 7.013090+6 0.000000+0 7.500000+6 2.028550-3 8.000000+6 1.902240-29340 3 16 4 8.500000+6 5.240460-2 9.000000+6 9.360230-2 9.500000+6 1.341840-19340 3 16 5 1.000000+7 1.703050-1 1.050000+7 2.011300-1 1.100000+7 2.251320-19340 3 16 6 1.150000+7 2.437910-1 1.200000+7 2.609120-1 1.250000+7 2.743300-19340 3 16 7 1.300000+7 2.866470-1 1.350000+7 2.949840-1 1.400000+7 2.929640-19340 3 16 8 1.450000+7 2.812010-1 1.500000+7 2.617280-1 1.550000+7 2.379530-19340 3 16 9 1.600000+7 2.156940-1 1.650000+7 1.945140-1 1.700000+7 1.766370-19340 3 16 10 1.750000+7 1.631950-1 1.800000+7 1.513570-1 1.850000+7 1.419020-19340 3 16 11 1.900000+7 1.342660-1 1.950000+7 1.280600-1 2.000000+7 1.229010-19340 3 16 12 9340 3 099999 9.323500+4 2.330250+2 0 0 0 09340 3 17 1 -1.304750+7-1.304750+7 0 0 1 159340 3 17 2 15 2 9340 3 17 3 1.310350+7 0.000000+0 1.350000+7 4.825970-6 1.400000+7 4.128520-49340 3 17 4 1.450000+7 1.981450-3 1.500000+7 5.167350-3 1.550000+7 9.895060-39340 3 17 5 1.600000+7 1.313970-2 1.650000+7 1.899130-2 1.700000+7 2.197020-29340 3 17 6 1.750000+7 2.436260-2 1.800000+7 2.582090-2 1.850000+7 2.633570-29340 3 17 7 1.900000+7 2.604490-2 1.950000+7 2.522350-2 2.000000+7 2.413870-29340 3 17 8 9340 3 099999 9.323500+4 2.330250+2 0 0 0 09340 3 18 1 1.937000+8 1.937000+8 0 0 1 3739340 3 18 2 373 2 9340 3 18 3 1.000000-5 2.668699+3 1.103037-5 2.540997+3 1.216691-5 2.419405+39340 3 18 4 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