JENDL-5 (Neutron sublibrary (activation cs)) Hf-182 0 0 0 0 7.218200+4 1.803875+2 0 0 6 17249 1451 1 0.000000+0 1.000000+0 0 0 0 67249 1451 2 1.000000+0 2.000000+7 0 0 10 57249 1451 3 2.936000+2 0.000000+0 4 0 273 267249 1451 4 72-Hf-182 JAEA EVAL-JUL09 K. Shibata (JAEA) 7249 1451 5 DIST-DEC21 20091001 7249 1451 6 ----JENDL-5 MATERIAL 7249 7249 1451 7 -----INCIDENT NEUTRON DATA 7249 1451 8 ------ENDF-6 FORMAT 7249 1451 9 7249 1451 10 History 7249 1451 11 09-07 Evaluated by K. Shibata. 7249 1451 12 09-10 Compiled by K. Shibata. 7249 1451 13 21-11 revised by O.Iwamoto 7249 1451 14 (MF8/MT4,16,17,22,28,32,102-107) added 7249 1451 15 7249 1451 16 MF= 1 General information 7249 1451 17 MT=451 Descriptive data and directory 7249 1451 18 7249 1451 19 MF= 2 Resonance parameters 7249 1451 20 MT=151 Resolved and unresolved resonance parameters 7249 1451 21 No resovled resonance parameters are given. 7249 1451 22 The 1/v-shaped capture cross section is assumed below 65 eV.7249 1451 23 At 0.0253 eV, the cross section is normalized to the value 7249 1451 24 of 133 b, which was obtained by Vockenhuber et al./1/ 7249 1451 25 The scattering cross section was calculated from 4*pi*R**2, 7249 1451 26 where the scattering radius R was obtained in the unresolved7249 1451 27 resonance region: R=8.020 fm. 7249 1451 28 Unresolved resonance region: 65 eV - 650 keV 7249 1451 29 The parameters were obtained by fitting to the total and 7249 1451 30 capture cross sections calculated from POD /2/. The 7249 1451 31 unresolved parameters should be used only for self-shielding7249 1451 32 calculation. 7249 1451 33 7249 1451 34 Thermal cross sections and resonance integrals at 300 K 7249 1451 35 ---------------------------------------------------------- 7249 1451 36 0.0253 eV res. integ. (*) 7249 1451 37 (barns) (barns) 7249 1451 38 ---------------------------------------------------------- 7249 1451 39 Total 1.4121E+02 7249 1451 40 Elastic 8.1067E+00 7249 1451 41 n,gamma 1.3306E+02 6.5866E+01 7249 1451 42 ---------------------------------------------------------- 7249 1451 43 (*) Integrated from 0.5 eV to 10 MeV. 7249 1451 44 7249 1451 45 MF= 3 Neutron cross sections 7249 1451 46 MT= 1 Total cross section 7249 1451 47 Calculated with POD code /2/. 7249 1451 48 7249 1451 49 MT= 2 Elastic scattering cross section 7249 1451 50 Obtained by subtracting non-elastic cross sections from total 7249 1451 51 cross sections. 7249 1451 52 7249 1451 53 MT= 3 Non-elastic cross section 7249 1451 54 Sum of partial non-elastic cross sections. 7249 1451 55 7249 1451 56 MT= 4,51-91 (n,n') cross section 7249 1451 57 Calculated with POD code /2/. 7249 1451 58 7249 1451 59 MT= 16 (n,2n) cross section 7249 1451 60 Calculated with POD code /2/. 7249 1451 61 7249 1451 62 MT= 17 (n,3n) cross section 7249 1451 63 Calculated with POD code /2/. 7249 1451 64 7249 1451 65 MT= 22 (n,na) cross section 7249 1451 66 Calculated with POD code /2/. 7249 1451 67 7249 1451 68 MT= 28 (n,np) cross section 7249 1451 69 Calculated with POD code /2/. 7249 1451 70 7249 1451 71 MT= 32 (n,nd) cross section 7249 1451 72 Calculated with POD code /2/. 7249 1451 73 7249 1451 74 MT=102 Capture cross section 7249 1451 75 Calculated with POD code /2/. 7249 1451 76 The gamma-ray strength function was renormalized by 7249 1451 77 considering the Maxwellian-averaged cross sections measured 7249 1451 78 by Vockenhuber et al./3/ 7249 1451 79 7249 1451 80 MT=103 (n,p) cross section 7249 1451 81 Calculated with POD code /2/. 7249 1451 82 7249 1451 83 MT=104 (n,d) cross section 7249 1451 84 Calculated with POD code /2/. 7249 1451 85 7249 1451 86 MT=105 (n,t) cross section 7249 1451 87 Calculated with POD code /2/. 7249 1451 88 7249 1451 89 MT=106 (n,He3) cross section 7249 1451 90 Calculated with POD code /2/. 7249 1451 91 7249 1451 92 MT=107 (n,a) cross section 7249 1451 93 Calculated with POD code /2/. 7249 1451 94 7249 1451 95 MT=203 (n,xp) cross section 7249 1451 96 Calculated with POD code /2/. 7249 1451 97 7249 1451 98 MT=204 (n,xd) cross section 7249 1451 99 Calculated with POD code /2/. 7249 1451 100 7249 1451 101 MT=205 (n,xt) cross section 7249 1451 102 Calculated with POD code /2/. 7249 1451 103 7249 1451 104 MT=206 (n,xHe3) cross section 7249 1451 105 Calculated with POD code /2/. 7249 1451 106 7249 1451 107 MT=207 (n,xa) cross section 7249 1451 108 Calculated with POD code /2/. 7249 1451 109 7249 1451 110 MF= 4 Angular distributions of emitted neutrons 7249 1451 111 MT= 2 Elastic scattering 7249 1451 112 Calculated with POD code /2/. 7249 1451 113 7249 1451 114 MF= 6 Energy-angle distributions of emitted particles 7249 1451 115 MT= 16 (n,2n) reaction 7249 1451 116 Neutron spectra calculated with POD/2/. 7249 1451 117 7249 1451 118 MT= 17 (n,3n) reaction 7249 1451 119 Neutron spectra calculated with POD/2/. 7249 1451 120 7249 1451 121 MT= 22 (n,na) reaction 7249 1451 122 Neutron spectra calculated with POD/2/. 7249 1451 123 7249 1451 124 MT= 28 (n,np) reaction 7249 1451 125 Neutron spectra calculated with POD/2/. 7249 1451 126 7249 1451 127 MT= 32 (n,nd) reaction 7249 1451 128 Neutron spectra calculated with POD/2/. 7249 1451 129 7249 1451 130 MT= 51 (n,n') reaction 7249 1451 131 Neutron angular distributions calculated with POD/2/. 7249 1451 132 7249 1451 133 MT= 52 (n,n') reaction 7249 1451 134 Neutron angular distributions calculated with POD/2/. 7249 1451 135 7249 1451 136 MT= 53 (n,n') reaction 7249 1451 137 Neutron angular distributions calculated with POD/2/. 7249 1451 138 7249 1451 139 MT= 54 (n,n') reaction 7249 1451 140 Neutron angular distributions calculated with POD/2/. 7249 1451 141 7249 1451 142 MT= 55 (n,n') reaction 7249 1451 143 Neutron angular distributions calculated with POD/2/. 7249 1451 144 7249 1451 145 MT= 56 (n,n') reaction 7249 1451 146 Neutron angular distributions calculated with POD/2/. 7249 1451 147 7249 1451 148 MT= 57 (n,n') reaction 7249 1451 149 Neutron angular distributions calculated with POD/2/. 7249 1451 150 7249 1451 151 MT= 58 (n,n') reaction 7249 1451 152 Neutron angular distributions calculated with POD/2/. 7249 1451 153 7249 1451 154 MT= 59 (n,n') reaction 7249 1451 155 Neutron angular distributions calculated with POD/2/. 7249 1451 156 7249 1451 157 MT= 91 (n,n') reaction 7249 1451 158 Neutron spectra calculated with POD/2/. 7249 1451 159 7249 1451 160 MT= 203 (n,xp) reaction 7249 1451 161 Proton spectra calculated with POD/2/. 7249 1451 162 7249 1451 163 MT= 204 (n,xd) reaction 7249 1451 164 Deuteron spectra calculated with POD/2/. 7249 1451 165 7249 1451 166 MT= 205 (n,xt) reaction 7249 1451 167 Triton spectra calculated with POD/2/. 7249 1451 168 7249 1451 169 MT= 206 (n,xHe3) reaction 7249 1451 170 He3 spectra calculated with POD/2/. 7249 1451 171 7249 1451 172 MT= 207 (n,xa) reaction 7249 1451 173 Alpha spectra calculated with POD/2/. 7249 1451 174 7249 1451 175 MF=12 Gamma-ray multiplicities 7249 1451 176 MT= 3 Non-elastic gamma emission 7249 1451 177 Calculated with POD code /2/. 7249 1451 178 7249 1451 179 MF=14 Gamma-ray angular distributions 7249 1451 180 MT= 3 Non-elastic gamma emission 7249 1451 181 Assumed to be isotropic. 7249 1451 182 7249 1451 183 MF=15 Gamma-ray spectra 7249 1451 184 MT= 3 Non-elastic gamma emission 7249 1451 185 Calculated with POD code /2/. 7249 1451 186 7249 1451 187 7249 1451 188 7249 1451 189 *************************************************************** 7249 1451 190 * Nuclear Model Calculations with POD Code /2/ * 7249 1451 191 *************************************************************** 7249 1451 192 1. Theoretical models 7249 1451 193 The POD code is based on the spherical optical model, the 7249 1451 194 distorted-wave Born approximaiton (DWBA), one-component exciton 7249 1451 195 preequilibrium model, and the Hauser-Feshbach-Moldauer statis- 7249 1451 196 tical model. With the preequilibrim model, semi-empirical 7249 1451 197 pickup and knockout process can be taken into account for 7249 1451 198 composite-particle emission. The gamma-ray emission from the 7249 1451 199 compound nucleus can be calculated within the framework of the 7249 1451 200 exciton model. The code is capable of reading in particle 7249 1451 201 transmission coefficients calculated by separate spherical or 7249 1451 202 coupled-channel optical model code. 7249 1451 203 7249 1451 204 2. Optical model parameters 7249 1451 205 Neutrons: 7249 1451 206 Coupled-channel optical model parameters /4/ 7249 1451 207 Protons: 7249 1451 208 Koning and Delaroche /5/ 7249 1451 209 Deuterons: 7249 1451 210 Lohr and Haeberli /6/ 7249 1451 211 Tritons: 7249 1451 212 Becchetti and Greenlees /7/ 7249 1451 213 He-3: 7249 1451 214 Becchetti and Greenlees /7/ 7249 1451 215 Alphas: 7249 1451 216 Lemos /8/ potentials modified by Arthur and Young /9/ 7249 1451 217 7249 1451 218 3. Level scheme of Hf-182 7249 1451 219 ------------------------- 7249 1451 220 No. Ex(MeV) J PI 7249 1451 221 ------------------------- 7249 1451 222 0 0.00000 0 + 7249 1451 223 1 0.09779 2 + 7249 1451 224 2 0.32218 4 + 7249 1451 225 3 0.66628 6 + 7249 1451 226 4 0.81840 1 + 7249 1451 227 5 0.90590 1 + 7249 1451 228 6 1.02200 1 + 7249 1451 229 7 1.03400 0 + 7249 1451 230 8 1.12208 8 + 7249 1451 231 9 1.17288 8 - 7249 1451 232 ------------------------- 7249 1451 233 Levels above 1.18288 MeV are assumed to be continuous. 7249 1451 234 7249 1451 235 4. Level density parameters 7249 1451 236 Energy-dependent parameters of Mengoni-Nakajima /10/ were used. 7249 1451 237 ---------------------------------------------------------- 7249 1451 238 Nuclei a* Pair Esh T E0 Ematch Elv_max 7249 1451 239 1/MeV MeV MeV MeV MeV MeV MeV 7249 1451 240 ---------------------------------------------------------- 7249 1451 241 Hf-183 22.017 0.887 1.653 0.468 -0.617 4.950 0.317 7249 1451 242 Hf-182 21.382 1.779 1.731 0.496 0.040 6.272 1.173 7249 1451 243 Hf-181 21.427 0.892 1.426 0.481 -0.588 4.988 0.600 7249 1451 244 Hf-180 20.861 1.789 1.577 0.563 -0.693 7.523 1.651 7249 1451 245 Lu-182 21.223 0.000 1.608 0.534 -2.170 5.212 0.000 7249 1451 246 Lu-181 20.436 0.892 1.859 0.543 -1.259 6.126 0.000 7249 1451 247 Lu-180 21.024 0.000 1.226 0.332 -0.102 1.567 0.562 7249 1451 248 Yb-180 21.180 1.789 2.100 0.482 0.168 6.059 0.000 7249 1451 249 Yb-179 21.625 0.897 1.664 0.464 -0.493 4.789 0.000 7249 1451 250 Yb-178 20.978 1.799 1.440 0.533 -0.244 6.840 0.576 7249 1451 251 ---------------------------------------------------------- 7249 1451 252 7249 1451 253 5. Gamma-ray strength functions 7249 1451 254 M1, E2: Standard Lorentzian (SLO) 7249 1451 255 E1 : Generalized Lorentzian (GLO) /11/ 7249 1451 256 7249 1451 257 6. Preequilibrium process 7249 1451 258 Preequilibrium is on for n, p, d, t, He-3, and alpha. 7249 1451 259 Preequilibrium capture is on. 7249 1451 260 7249 1451 261 References 7249 1451 262 1) C.Vockenhuber et al., Phys. Rev. C77, 044608 (2008). 7249 1451 263 2) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 7249 1451 264 3) C.Vockenhuber et al., Phys. Rev. C75, 015804 (2007). 7249 1451 265 4) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 7249 1451 266 5) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 7249 1451 267 6) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 7249 1451 268 7) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization 7249 1451 269 Phenomena in Nuclear Reactions," p.682, The University 7249 1451 270 of Wisconsin Press (1971). 7249 1451 271 8) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 7249 1451 272 9) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 7249 1451 273 10) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 7249 1451 274 (1994). 7249 1451 275 11) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990). 7249 1451 276 7249 1451 277 1 451 303 17249 1451 278 2 151 4 17249 1451 279 3 4 20 17249 1451 280 3 16 10 17249 1451 281 3 17 7 17249 1451 282 3 22 8 17249 1451 283 3 28 7 17249 1451 284 3 32 5 17249 1451 285 3 102 106 17249 1451 286 3 103 10 17249 1451 287 3 104 8 17249 1451 288 3 105 8 17249 1451 289 3 106 5 17249 1451 290 3 107 11 17249 1451 291 8 4 2 17249 1451 292 8 16 2 17249 1451 293 8 17 2 17249 1451 294 8 22 2 17249 1451 295 8 28 2 17249 1451 296 8 32 2 17249 1451 297 8 102 2 17249 1451 298 8 103 2 17249 1451 299 8 104 2 17249 1451 300 8 105 2 17249 1451 301 8 106 2 17249 1451 302 8 107 2 17249 1451 303 7249 1 099999 7249 0 0 0 7.218200+4 1.803875+2 0 0 1 07249 2151 1 7.218200+4 1.000000+0 0 0 1 07249 2151 2 6.500000+1 6.500000+5 0 0 0 07249 2151 3 0.000000+0 8.020300-1 0 0 0 07249 2151 4 7249 2 099999 7249 0 0 0 7.218200+4 1.803875+2 0 0 0 07249 3 4 1 0.000000+0-9.779000+4 0 0 1 507249 3 4 2 50 2 7249 3 4 3 9.833211+4 0.000000+0 1.000000+5 6.359000-2 2.000000+5 6.199000-17249 3 4 4 3.000000+5 1.023000+0 3.239660+5 1.095857+0 4.000000+5 1.341040+07249 3 4 5 5.000000+5 1.601550+0 6.000000+5 1.820400+0 6.699736+5 1.951810+07249 3 4 6 7.000000+5 2.008205+0 8.000000+5 2.170810+0 8.229369+5 2.186396+07249 3 4 7 9.000000+5 2.399363+0 9.109220+5 2.410012+0 1.000000+6 2.634967+07249 3 4 8 1.027666+6 2.690870+0 1.039732+6 2.725986+0 1.128300+6 3.023357+07249 3 4 9 1.179382+6 3.194867+0 1.189437+6 3.228627+0 1.250000+6 3.439792+07249 3 4 10 1.500000+6 3.564348+0 2.000000+6 3.638358+0 2.500000+6 3.587103+07249 3 4 11 3.000000+6 3.508436+0 3.500000+6 3.419320+0 4.000000+6 3.354814+07249 3 4 12 4.500000+6 3.307827+0 5.000000+6 3.262265+0 5.500000+6 3.208839+07249 3 4 13 6.000000+6 3.152783+0 6.500000+6 3.100791+0 7.000000+6 3.027882+07249 3 4 14 7.500000+6 2.339959+0 8.000000+6 1.805857+0 8.500000+6 1.369697+07249 3 4 15 9.000000+6 1.137965+0 9.500000+6 9.768443-1 1.000000+7 8.764984-17249 3 4 16 1.100000+7 7.483938-1 1.200000+7 6.679943-1 1.300000+7 6.084385-17249 3 4 17 1.400000+7 5.605336-1 1.450000+7 5.397286-1 1.500000+7 5.230115-17249 3 4 18 1.600000+7 4.882834-1 1.700000+7 4.595441-1 1.800000+7 4.332107-17249 3 4 19 1.900000+7 4.089770-1 2.000000+7 3.873604-1 7249 3 4 20 7249 3 099999 7.218200+4 1.803875+2 0 0 0 07249 3 16 1 -6.717996+6-6.717996+6 0 0 1 197249 3 16 2 19 2 7249 3 16 3 6.755238+6 0.000000+0 7.000000+6 2.834000-2 7.500000+6 6.807000-17249 3 16 4 8.000000+6 1.187000+0 8.500000+6 1.601000+0 9.000000+6 1.814000+07249 3 16 5 9.500000+6 1.958000+0 1.000000+7 2.041000+0 1.100000+7 2.132000+07249 3 16 6 1.200000+7 2.174000+0 1.300000+7 2.196000+0 1.400000+7 2.066000+07249 3 16 7 1.450000+7 1.879000+0 1.500000+7 1.651000+0 1.600000+7 1.216000+07249 3 16 8 1.700000+7 9.122000-1 1.800000+7 7.227000-1 1.900000+7 6.010000-17249 3 16 9 2.000000+7 5.199000-1 7249 3 16 10 7249 3 099999 7.218200+4 1.803875+2 0 0 0 07249 3 17 1 -1.241280+7-1.241280+7 0 0 1 107249 3 17 2 10 2 7249 3 17 3 1.248161+7 0.000000+0 1.300000+7 1.729000-3 1.400000+7 1.499000-17249 3 17 4 1.450000+7 3.447000-1 1.500000+7 5.786000-1 1.600000+7 1.027000+07249 3 17 5 1.700000+7 1.340000+0 1.800000+7 1.534000+0 1.900000+7 1.656000+07249 3 17 6 2.000000+7 1.733000+0 7249 3 17 7 7249 3 099999 7.218200+4 1.803875+2 0 0 0 07249 3 22 1 1.214819+6 1.214819+6 0 0 1 147249 3 22 2 14 2 7249 3 22 3 1.000000-5 0.000000+0 2.530000-2 0.000000+0 1.000000+7 0.000000+07249 3 22 4 1.100000+7 2.448000-8 1.200000+7 6.416000-7 1.300000+7 2.860000-67249 3 22 5 1.400000+7 1.032000-5 1.450000+7 1.845000-5 1.500000+7 3.337000-57249 3 22 6 1.600000+7 9.423000-5 1.700000+7 2.257000-4 1.800000+7 4.517000-47249 3 22 7 1.900000+7 7.678000-4 2.000000+7 1.150000-3 7249 3 22 8 7249 3 099999 7.218200+4 1.803875+2 0 0 0 07249 3 28 1 -8.607877+6-8.607877+6 0 0 1 117249 3 28 2 11 2 7249 3 28 3 8.655595+6 0.000000+0 1.200000+7 0.000000+0 1.300000+7 2.857000-87249 3 28 4 1.400000+7 1.058000-6 1.450000+7 4.286000-6 1.500000+7 1.160000-57249 3 28 5 1.600000+7 7.008000-5 1.700000+7 2.763000-4 1.800000+7 7.693000-47249 3 28 6 1.900000+7 1.651000-3 2.000000+7 2.960000-3 7249 3 28 7 7249 3 099999 7.218200+4 1.803875+2 0 0 0 07249 3 32 1 -1.250889+7-1.250889+7 0 0 1 67249 3 32 2 6 2 7249 3 32 3 1.257823+7 0.000000+0 1.600000+7 0.000000+0 1.700000+7 1.843000-87249 3 32 4 1.800000+7 8.005000-7 1.900000+7 1.028000-5 2.000000+7 6.909000-57249 3 32 5 7249 3 099999 7.218200+4 1.803875+2 0 0 0 07249 3102 1 5.298871+6 5.298871+6 0 0 1 3077249 3102 2 307 2 7249 3102 3 1.000000-5 6.689833+3 1.103037-5 6.369718+3 1.216691-5 6.064922+37249 3102 4 1.342055-5 5.774710+3 1.480336-5 5.498385+3 1.632865-5 5.235282+37249 3102 5 1.801111-5 4.984769+3 1.986691-5 4.746244+3 2.191394-5 4.519132+37249 3102 6 2.417189-5 4.302888+3 2.666248-5 4.096991+3 2.940971-5 3.900946+37249 3102 7 3.243999-5 3.714282+3 3.578251-5 3.536551+3 3.946943-5 3.367324+37249 3102 8 4.353624-5 3.206194+3 4.802208-5 3.052775+3 5.297013-5 2.906697+37249 3102 9 5.842801-5 2.767609+3 6.444825-5 2.635176+3 7.108881-5 2.509081+37249 3102 10 7.841358-5 2.389019+3 8.649308-5 2.274703+3 9.540506-5 2.165856+37249 3102 11 1.052353-4 2.062218+3 1.160784-4 1.963539+3 1.280388-4 1.869582+37249 3102 12 1.412315-4 1.780121+3 1.557836-4 1.694941+3 1.718351-4 1.613836+37249 3102 13 1.895404-4 1.536613+3 2.090701-4 1.463084+3 2.306120-4 1.393075+37249 3102 14 2.543736-4 1.326415+3 2.805835-4 1.262945+3 3.094939-4 1.202512+37249 3102 15 3.413832-4 1.144970+3 3.765583-4 1.090183+3 4.153577-4 1.038016+37249 3102 16 4.581549-4 9.883463+2 5.053618-4 9.410531+2 5.574328-4 8.960229+27249 3102 17 6.148689-4 8.531474+2 6.782232-4 8.123235+2 7.481052-4 7.734531+27249 3102 18 8.251877-4 7.364427+2 9.102125-4 7.012032+2 1.003998-3 6.676501+27249 3102 19 1.107447-3 6.357024+2 1.221555-3 6.052835+2 1.347420-3 5.763201+27249 3102 20 1.486254-3 5.487427+2 1.639393-3 5.224849+2 1.808311-3 4.974835+27249 3102 21 1.994634-3 4.736785+2 2.200155-3 4.510126+2 2.426853-3 4.294314+27249 3102 22 2.676908-3 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