JENDL-5 (Neutron sublibrary (activation cs)) Cm-249 0 0 0 0 9.624900+4 2.469360+2 0 0 6 19652 1451 1 0.000000+0 1.000000+0 0 0 0 69652 1451 2 1.000000+0 2.000000+7 0 0 10 59652 1451 3 2.936000+2 0.000000+0 4 0 316 149652 1451 4 96-Cm-249 JAEA+ EVAL-FEB10 O.Iwamoto, T.Nakagawa, et al. 9652 1451 5 DIST-DEC21 20100303 9652 1451 6 ----JENDL-5 MATERIAL 9652 9652 1451 7 -----INCIDENT NEUTRON DATA 9652 1451 8 ------ENDF-6 FORMAT 9652 1451 9 9652 1451 10 History 9652 1451 11 07-08 Theoretical calculation was performed with CCONE code. 9652 1451 12 08-03 Recalculation with CCONE code was performed. 9652 1451 13 Data were compiled as JENDL/AC-2008/1/. 9652 1451 14 10-02 Data of prompt gamma rays due to fission were given. 9652 1451 15 10-03 Covariance data were given. 9652 1451 16 9652 1451 17 21-11 revised by O.Iwamoto 9652 1451 18 (MF3/MT19-21,38) deleted 9652 1451 19 (MF8/MT16-18,37,102) JENDL/AD-2017 adopted 9652 1451 20 (MF8/MT4) added 9652 1451 21 9652 1451 22 MF=1 General information 9652 1451 23 MT=452 Number of Neutrons per fission 9652 1451 24 Sum of MT's=455 and 456. 9652 1451 25 9652 1451 26 MT=455 Delayed neutron data 9652 1451 27 (Same as JENDL-3.3) 9652 1451 28 Estimated from Tuttle's systematics/2/. 9652 1451 29 9652 1451 30 MT=456 Number of prompt neutrons per fission 9652 1451 31 (Same as JENDL-3.3) 9652 1451 32 Estimated from Howerton's sytematics/3/. 9652 1451 33 9652 1451 34 9652 1451 35 MF= 2 Resonance parameters 9652 1451 36 MT=151 9652 1451 37 No resonance parameters are given. 9652 1451 38 9652 1451 39 9652 1451 40 Thermal cross sections and resonance integrals (at 300K) 9652 1451 41 ------------------------------------------------------- 9652 1451 42 0.0253 eV reson. integ.(*) 9652 1451 43 (barns) (barns) 9652 1451 44 ------------------------------------------------------- 9652 1451 45 total 21.57 9652 1451 46 elastic 9.92 9652 1451 47 fission 10.00 438 9652 1451 48 capture 1.60 56.9 9652 1451 49 ------------------------------------------------------- 9652 1451 50 (*) In the energy range from 0.5 eV to 10 MeV. 9652 1451 51 9652 1451 52 9652 1451 53 MF= 3 Neutron cross sections 9652 1451 54 Below 3.1 eV: 9652 1451 55 * Elastic scattering cross section is 9.9 b calculated from 9652 1451 56 scattering radius of 8.876 fm/4/. 9652 1451 57 * Capture cross section is in the 1/v shape, and 1.6 b at 9652 1451 58 0.0253 eV /5/. 9652 1451 59 * Fission cross section is in the 1/v shape, and 10 b at 9652 1451 60 0.0253 eV which was estimated by assuming that the cross- 9652 1451 61 section ratio of capture and fission was the same as that 9652 1451 62 at 1 eV calculated with CCONE code/4/. 9652 1451 63 9652 1451 64 Above 3.1 eV: 9652 1451 65 Cross sections were calculated with CCONE code/4/. 9652 1451 66 9652 1451 67 MT= 1 Total cross section 9652 1451 68 The cross section was calculated with CC OMP of Soukhovitskii 9652 1451 69 et al./6/ 9652 1451 70 9652 1451 71 9652 1451 72 MF= 4 Angular distributions of secondary neutrons 9652 1451 73 MT=2 Elastic scattering 9652 1451 74 Calculated with CCONE code. 9652 1451 75 9652 1451 76 MT=18 Fission 9652 1451 77 Isotropic distributions in the laboratory system were assumed.9652 1451 78 9652 1451 79 9652 1451 80 MF= 5 Energy distributions of secondary neutrons 9652 1451 81 MT=18 Prompt neutrons 9652 1451 82 Calculated with CCONE code/4/. 9652 1451 83 9652 1451 84 9652 1451 85 MF= 6 Energy-angle distributions 9652 1451 86 Calculated with CCONE code. 9652 1451 87 Distributions from fission (MT=18) are not included. 9652 1451 88 9652 1451 89 9652 1451 90 MF=12 Photon production multiplicities 9652 1451 91 MT=18 Fission 9652 1451 92 Calculated from the total energy released by the prompt 9652 1451 93 gamma-rays due to fission which was estimated from its 9652 1451 94 systematics, and the average energy of gamma-rays. 9652 1451 95 9652 1451 96 9652 1451 97 MF=14 Photon angular distributions 9652 1451 98 MT=18 Fission 9652 1451 99 Isotoropic distributions were assumed. 9652 1451 100 9652 1451 101 9652 1451 102 MF=15 Continuous photon energy spectra 9652 1451 103 MT=18 Fission 9652 1451 104 Experimental data measured by Verbinski et al./7/ for 9652 1451 105 Pu-239 thermal fission were adopted. 9652 1451 106 9652 1451 107 9652 1451 108 MF=31 Covariances of average number of neutrons per fission 9652 1451 109 MT=452 Number of neutrons per fission 9652 1451 110 Sum of covariances for MT=455 and MT=456. 9652 1451 111 9652 1451 112 MT=455 9652 1451 113 Error of 15% was assumed. 9652 1451 114 9652 1451 115 MT=456 9652 1451 116 Covariance was obtained by fitting a linear function to the 9652 1451 117 at 0.0 and 5.0 MeV with an uncertainty of 5%. 9652 1451 118 9652 1451 119 9652 1451 120 MF=33 Covariances of neutron cross sections 9652 1451 121 Covariances were given to all the cross sections by using 9652 1451 122 KALMAN code/8/ and the covariances of model parameters 9652 1451 123 used in the cross-section calculations. 9652 1451 124 9652 1451 125 For the following cross sections, standard deviations in the 9652 1451 126 energy region below 3.1 eV were assumed as follows: 9652 1451 127 9652 1451 128 Total 33 % 9652 1451 129 Elastic scattering 50 % 9652 1451 130 Fission 50 % estimated from experimental data 9652 1451 131 Capture 50 % 9652 1451 132 9652 1451 133 9652 1451 134 MF=34 Covariances for Angular Distributions 9652 1451 135 MT=2 Elastic scattering 9652 1451 136 Covariances were given only to P1 components. 9652 1451 137 9652 1451 138 9652 1451 139 MF=35 Covariances for Energy Distributions 9652 1451 140 MT=18 Fission spectra 9652 1451 141 Estimated with CCONE and KALMAN codes. 9652 1451 142 9652 1451 143 9652 1451 144 ***************************************************************** 9652 1451 145 Calculation with CCONE code 9652 1451 146 ***************************************************************** 9652 1451 147 9652 1451 148 Models and parameters used in the CCONE/4/ calculation 9652 1451 149 1) Coupled channel optical model 9652 1451 150 Levels in the rotational band were included. Optical model 9652 1451 151 potential and coupled levels are shown in Table 1. 9652 1451 152 9652 1451 153 2) Two-component exciton model/9/ 9652 1451 154 * Global parametrization of Koning-Duijvestijn/10/ 9652 1451 155 was used. 9652 1451 156 * Gamma emission channel/11/ was added to simulate direct 9652 1451 157 and semi-direct capture reaction. 9652 1451 158 9652 1451 159 3) Hauser-Feshbach statistical model 9652 1451 160 * Moldauer width fluctuation correction/12/ was included. 9652 1451 161 * Neutron, gamma and fission decay channel were included. 9652 1451 162 * Transmission coefficients of neutrons were taken from 9652 1451 163 coupled channel calculation in Table 1. 9652 1451 164 * The level scheme of the target is shown in Table 2. 9652 1451 165 * Level density formula of constant temperature and Fermi-gas 9652 1451 166 model were used with shell energy correction and collective 9652 1451 167 enhancement factor. Parameters are shown in Table 3. 9652 1451 168 * Fission channel: 9652 1451 169 Double humped fission barriers were assumed. 9652 1451 170 Fission barrier penetrabilities were calculated with 9652 1451 171 Hill-Wheler formula/13/. Fission barrier parameters were 9652 1451 172 shown in Table 4. Transition state model was used and 9652 1451 173 continuum levels are assumed above the saddles. The level 9652 1451 174 density parameters for inner and outer saddles are shown in 9652 1451 175 Tables 5 and 6, respectively. 9652 1451 176 * Gamma-ray strength function of Kopecky et al/14/,/15/ 9652 1451 177 was used. The prameters are shown in Table 7. 9652 1451 178 9652 1451 179 9652 1451 180 ------------------------------------------------------------------9652 1451 181 Tables 9652 1451 182 ------------------------------------------------------------------9652 1451 183 9652 1451 184 Table 1. Coupled channel calculation 9652 1451 185 -------------------------------------------------- 9652 1451 186 * rigid rotor model was applied 9652 1451 187 * coupled levels = 0,1,2,5,6,10 (see Table 2) 9652 1451 188 * optical potential parameters /6/ 9652 1451 189 Volume: 9652 1451 190 V_0 = 49.97 MeV 9652 1451 191 lambda_HF = 0.01004 1/MeV 9652 1451 192 C_viso = 15.9 MeV 9652 1451 193 A_v = 12.04 MeV 9652 1451 194 B_v = 81.36 MeV 9652 1451 195 E_a = 385 MeV 9652 1451 196 r_v = 1.2568 fm 9652 1451 197 a_v = 0.633 fm 9652 1451 198 Surface: 9652 1451 199 W_0 = 17.2 MeV 9652 1451 200 B_s = 11.19 MeV 9652 1451 201 C_s = 0.01361 1/MeV 9652 1451 202 C_wiso = 23.5 MeV 9652 1451 203 r_s = 1.1803 fm 9652 1451 204 a_s = 0.601 fm 9652 1451 205 Spin-orbit: 9652 1451 206 V_so = 5.75 MeV 9652 1451 207 lambda_so = 0.005 1/MeV 9652 1451 208 W_so = -3.1 MeV 9652 1451 209 B_so = 160 MeV 9652 1451 210 r_so = 1.1214 fm 9652 1451 211 a_so = 0.59 fm 9652 1451 212 Coulomb: 9652 1451 213 C_coul = 1.3 9652 1451 214 r_c = 1.2452 fm 9652 1451 215 a_c = 0.545 fm 9652 1451 216 Deformation: 9652 1451 217 beta_2 = 0.213 9652 1451 218 beta_4 = 0.066 9652 1451 219 beta_6 = 0.0015 9652 1451 220 9652 1451 221 * Calculated strength function 9652 1451 222 S0= 1.16e-4 S1= 3.67e-4 R'= 8.88 fm (En=1 keV) 9652 1451 223 -------------------------------------------------- 9652 1451 224 9652 1451 225 Table 2. Level Scheme of Cm-249 9652 1451 226 ------------------- 9652 1451 227 No. Ex(MeV) J PI 9652 1451 228 ------------------- 9652 1451 229 0 0.00000 1/2 + * 9652 1451 230 1 0.02623 3/2 + * 9652 1451 231 2 0.04820 5/2 + * 9652 1451 232 3 0.04876 7/2 + 9652 1451 233 4 0.11000 9/2 + 9652 1451 234 5 0.11015 7/2 + * 9652 1451 235 6 0.14600 9/2 + * 9652 1451 236 7 0.20800 3/2 + 9652 1451 237 8 0.22000 9/2 + 9652 1451 238 9 0.24201 5/2 + 9652 1451 239 10 0.24217 11/2 + * 9652 1451 240 11 0.28901 7/2 + 9652 1451 241 12 0.30000 11/2 + 9652 1451 242 ------------------- 9652 1451 243 *) Coupled levels in CC calculation 9652 1451 244 9652 1451 245 Table 3. Level density parameters 9652 1451 246 -------------------------------------------------------- 9652 1451 247 Nuclide a* Pair Eshell T E0 Ematch 9652 1451 248 1/MeV MeV MeV MeV MeV MeV 9652 1451 249 -------------------------------------------------------- 9652 1451 250 Cm-250 19.1626 1.5179 2.7178 0.3404 0.2175 3.3179 9652 1451 251 Cm-249 19.0966 0.7605 2.3053 0.3754 -0.8571 2.9585 9652 1451 252 Cm-248 18.5357 1.5240 2.0504 0.3482 0.2818 3.2555 9652 1451 253 Cm-247 18.3955 0.7635 1.7794 0.3734 -0.6804 2.7533 9652 1451 254 Cm-246 18.8984 1.5302 1.7310 0.3608 0.1621 3.4286 9652 1451 255 -------------------------------------------------------- 9652 1451 256 9652 1451 257 Table 4. Fission barrier parameters 9652 1451 258 ---------------------------------------- 9652 1451 259 Nuclide V_A hw_A V_B hw_B 9652 1451 260 MeV MeV MeV MeV 9652 1451 261 ---------------------------------------- 9652 1451 262 Cm-250 5.500 1.040 4.400 0.600 9652 1451 263 Cm-249 5.500 0.750 5.100 0.430 9652 1451 264 Cm-248 6.100 1.040 4.950 0.600 9652 1451 265 Cm-247 5.400 0.800 5.650 0.650 9652 1451 266 Cm-246 6.300 1.040 5.100 0.600 9652 1451 267 ---------------------------------------- 9652 1451 268 9652 1451 269 Table 5. Level density above inner saddle 9652 1451 270 -------------------------------------------------------- 9652 1451 271 Nuclide a* Pair Eshell T E0 Ematch 9652 1451 272 1/MeV MeV MeV MeV MeV MeV 9652 1451 273 -------------------------------------------------------- 9652 1451 274 Cm-250 21.0788 1.7709 2.6000 0.2931 -0.2224 3.3709 9652 1451 275 Cm-249 21.0062 0.8872 2.6000 0.3388 -1.7502 3.0872 9652 1451 276 Cm-248 20.9336 1.5000 2.6000 0.3323 -1.0300 3.6000 9652 1451 277 Cm-247 20.8609 0.8908 2.6000 0.3256 -1.5320 2.8908 9652 1451 278 Cm-246 20.7882 1.6500 2.6000 0.3263 -0.7728 3.6500 9652 1451 279 -------------------------------------------------------- 9652 1451 280 9652 1451 281 Table 6. Level density above outer saddle 9652 1451 282 -------------------------------------------------------- 9652 1451 283 Nuclide a* Pair Eshell T E0 Ematch 9652 1451 284 1/MeV MeV MeV MeV MeV MeV 9652 1451 285 -------------------------------------------------------- 9652 1451 286 Cm-250 21.0788 1.7709 0.9400 0.3753 -0.1984 4.0709 9652 1451 287 Cm-249 19.0966 0.8872 0.9000 0.3432 -0.5123 2.4872 9652 1451 288 Cm-248 20.9336 1.7780 0.8600 0.3706 -0.1043 3.9780 9652 1451 289 Cm-247 20.8609 0.8908 0.8200 0.3573 -0.8210 2.8908 9652 1451 290 Cm-246 20.7882 1.7852 0.7800 0.3658 -0.0107 3.8852 9652 1451 291 -------------------------------------------------------- 9652 1451 292 9652 1451 293 Table 7. Gamma-ray strength function for Cm-250 9652 1451 294 -------------------------------------------------------- 9652 1451 295 * E1: ER = 11.44 (MeV) EG = 2.73 (MeV) SIG = 330.66 (mb) 9652 1451 296 ER = 14.22 (MeV) EG = 4.14 (MeV) SIG = 436.50 (mb) 9652 1451 297 * M1: ER = 6.51 (MeV) EG = 4.00 (MeV) SIG = 1.48 (mb) 9652 1451 298 * E2: ER = 10.00 (MeV) EG = 3.11 (MeV) SIG = 7.06 (mb) 9652 1451 299 -------------------------------------------------------- 9652 1451 300 9652 1451 301 9652 1451 302 References 9652 1451 303 1) O.Iwamoto et al.: J. Nucl. Sci. Technol., 46, 510 (2009). 9652 1451 304 2) R.J.Tuttle: INDC(NDS)-107/G+Special, p.29 (1979). 9652 1451 305 3) R.J.Howerton: Nucl. Sci. Eng., 62, 438 (1977). 9652 1451 306 4) O.Iwamoto: J. Nucl. Sci. Technol., 44, 687 (2007). 9652 1451 307 5) H.Diamond et al.: ANL-7330 (1967). 9652 1451 308 6) E.Sh.Soukhovitskii et al.: Phys. Rev. C72, 024604 (2005). 9652 1451 309 7) V.V.Verbinski et al.: Phys. Rev., C7, 1173 (1973). 9652 1451 310 8) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in 9652 1451 311 Japanese. 9652 1451 312 9) C.Kalbach: Phys. Rev. C33, 818 (1986). 9652 1451 313 10) A.J.Koning, M.C.Duijvestijn: Nucl. Phys. A744, 15 (2004). 9652 1451 314 11) J.M.Akkermans, H.Gruppelaar: Phys. Lett. 157B, 95 (1985). 9652 1451 315 12) P.A.Moldauer: Nucl. Phys. A344, 185 (1980). 9652 1451 316 13) D.L.Hill, J.A.Wheeler: Phys. Rev. 89, 1102 (1953). 9652 1451 317 14) J.Kopecky, M.Uhl: Phys. Rev. C41, 1941 (1990). 9652 1451 318 15) J.Kopecky, M.Uhl, R.E.Chrien: Phys. Rev. C47, 312 (1990). 9652 1451 319 9652 1451 320 1 451 334 19652 1451 321 2 151 4 19652 1451 322 3 4 30 19652 1451 323 3 16 14 19652 1451 324 3 17 10 19652 1451 325 3 18 146 19652 1451 326 3 37 6 19652 1451 327 3 102 177 19652 1451 328 8 4 2 19652 1451 329 8 16 2 19652 1451 330 8 17 2 19652 1451 331 8 18 2 19652 1451 332 8 37 2 19652 1451 333 8 102 2 19652 1451 334 9652 1 099999 9652 0 0 0 9.624900+4 2.469360+2 0 0 1 09652 2151 1 9.624900+4 1.000000+0 0 0 1 09652 2151 2 1.000000-5 3.100000+0 0 0 0 09652 2151 3 5.000000-1 8.887600-1 0 0 0 09652 2151 4 9652 2 099999 9652 0 0 0 9.624900+4 2.469360+2 0 0 0 09652 3 4 1 0.000000+0-2.622800+4 0 0 1 819652 3 4 2 81 2 9652 3 4 3 2.633420+4 0.000000+0 3.000000+4 1.788310-1 4.839820+4 4.358080-19652 3 4 4 4.895540+4 4.438744-1 4.895550+4 4.438758-1 5.000000+4 4.592040-19652 3 4 5 7.000000+4 7.694282-1 1.000000+5 1.125402+0 1.052230+5 1.174308+09652 3 4 6 1.104450+5 1.223207+0 1.104460+5 1.223217+0 1.106000+5 1.224543+09652 3 4 7 1.200000+5 1.306186+0 1.400000+5 1.448350+0 1.465910+5 1.487847+09652 3 4 8 1.700000+5 1.606287+0 2.000000+5 1.723487+0 2.088430+5 1.754394+09652 3 4 9 2.208910+5 1.842156+0 2.429880+5 1.949943+0 2.431510+5 1.951694+09652 3 4 10 2.500000+5 1.988222+0 2.901760+5 2.157114+0 3.000000+5 2.192676+09652 3 4 11 3.012150+5 2.197322+0 4.000000+5 2.409538+0 5.000000+5 2.530180+09652 3 4 12 6.000000+5 2.669314+0 7.000000+5 2.765449+0 8.000000+5 2.862451+09652 3 4 13 9.000000+5 2.918416+0 1.000000+6 2.943107+0 1.100000+6 2.981774+09652 3 4 14 1.200000+6 3.012279+0 1.300000+6 3.030564+0 1.400000+6 3.039851+09652 3 4 15 1.500000+6 3.029919+0 1.600000+6 3.015041+0 1.700000+6 2.979952+09652 3 4 16 1.800000+6 2.942476+0 1.900000+6 2.889458+0 2.000000+6 2.835720+09652 3 4 17 2.100000+6 2.771640+0 2.300000+6 2.645015+0 2.500000+6 2.515704+09652 3 4 18 2.700000+6 2.395663+0 3.000000+6 2.294532+0 3.500000+6 2.160161+09652 3 4 19 4.000000+6 2.084074+0 4.500000+6 2.080232+0 5.000000+6 1.996796+09652 3 4 20 5.500000+6 1.576317+0 6.000000+6 1.211581+0 6.500000+6 9.969776-19652 3 4 21 7.000000+6 8.664716-1 7.500000+6 7.728438-1 8.000000+6 7.132863-19652 3 4 22 8.500000+6 6.670551-1 9.000000+6 6.323226-1 9.500000+6 5.990445-19652 3 4 23 1.000000+7 5.716430-1 1.050000+7 5.472709-1 1.100000+7 5.231842-19652 3 4 24 1.150000+7 5.013766-1 1.200000+7 4.815997-1 1.250000+7 4.619038-19652 3 4 25 1.300000+7 4.410783-1 1.350000+7 4.232986-1 1.400000+7 4.078304-19652 3 4 26 1.450000+7 3.910219-1 1.500000+7 3.768964-1 1.550000+7 3.628996-19652 3 4 27 1.600000+7 3.503889-1 1.650000+7 3.381496-1 1.700000+7 3.276643-19652 3 4 28 1.750000+7 3.175029-1 1.800000+7 3.072631-1 1.850000+7 2.993468-19652 3 4 29 1.900000+7 2.890334-1 1.950000+7 2.825390-1 2.000000+7 2.754984-19652 3 4 30 9652 3 099999 9.624900+4 2.469360+2 0 0 0 09652 3 16 1 -4.713370+6-4.713370+6 0 0 1 329652 3 16 2 32 2 9652 3 16 3 4.732460+6 0.000000+0 5.000000+6 7.978650-2 5.500000+6 5.179870-19652 3 16 4 6.000000+6 7.705060-1 6.500000+6 8.297480-1 7.000000+6 8.574240-19652 3 16 5 7.500000+6 8.959140-1 8.000000+6 9.103200-1 8.500000+6 9.326270-19652 3 16 6 9.000000+6 9.678960-1 9.500000+6 1.011850+0 1.000000+7 1.053740+09652 3 16 7 1.050000+7 1.072770+0 1.100000+7 1.060190+0 1.150000+7 1.001170+09652 3 16 8 1.200000+7 9.070900-1 1.250000+7 7.912100-1 1.300000+7 6.740060-19652 3 16 9 1.350000+7 5.756870-1 1.400000+7 4.952340-1 1.450000+7 4.349560-19652 3 16 10 1.500000+7 3.783010-1 1.550000+7 3.495400-1 1.600000+7 3.239810-19652 3 16 11 1.650000+7 2.999950-1 1.700000+7 2.846410-1 1.750000+7 2.676220-19652 3 16 12 1.800000+7 2.589010-1 1.850000+7 2.442800-1 1.900000+7 2.398630-19652 3 16 13 1.950000+7 2.269920-1 2.000000+7 2.133140-1 9652 3 16 14 9652 3 099999 9.624900+4 2.469360+2 0 0 0 09652 3 17 1 -1.092640+7-1.092640+7 0 0 1 199652 3 17 2 19 2 9652 3 17 3 1.097060+7 0.000000+0 1.150000+7 1.329510-3 1.200000+7 2.325630-29652 3 17 4 1.250000+7 7.343200-2 1.300000+7 1.391070-1 1.350000+7 2.154100-19652 3 17 5 1.400000+7 2.636730-1 1.450000+7 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