JENDL-5 (Neutron sublibrary (activation cs)) Ca- 46 0 0 0 0 2.004600+4 4.555890+1 0 0 6 12043 1451 1 0.000000+0 0.000000+0 0 0 0 62043 1451 2 1.000000+0 2.000000+7 0 0 10 52043 1451 3 2.936000+2 0.000000+0 4 0 212 182043 1451 4 20-Ca- 46 JAEA EVAL-JUN06 K.Shibata 2043 1451 5 DIST-DEC21 20091228 2043 1451 6 ----JENDL-5 MATERIAL 2043 2043 1451 7 -----INCIDENT NEUTRON DATA 2043 1451 8 ------ENDF-6 FORMAT 2043 1451 9 2043 1451 10 History 2043 1451 11 06-06 Evaluated by K.Shibata. 2043 1451 12 09-12 Compiled by K.Shibata 2043 1451 13 21-11 revised by O.Iwamoto 2043 1451 14 (MF8/MT16,17,22,28,102,103,107) JENDL/AD-2017 adopted 2043 1451 15 (MF8/MT4) added 2043 1451 16 21-11 above 20 MeV, JENDL-4.0/HE merged by O.Iwamoto 2043 1451 17 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 2043 1451 18 2043 1451 19 2043 1451 20 MF=1 General information 2043 1451 21 MT=451 Descriptive data and dictionary 2043 1451 22 2043 1451 23 MF=2 Resonance parameters 2043 1451 24 MT=151 Resolved resonance parameters 2043 1451 25 No resonance parameters are given. 2043 1451 26 2043 1451 27 Thermal cross sections and resonance integrals at 300 K 2043 1451 28 ---------------------------------------------------------- 2043 1451 29 0.0253 eV res. integ. (*) 2043 1451 30 (barns) (barns) 2043 1451 31 ---------------------------------------------------------- 2043 1451 32 Total 3.6800E+00 2043 1451 33 Elastic 2.9325E+00 2043 1451 34 n,gamma 7.4023E-01 3.6492E-01 2043 1451 35 ---------------------------------------------------------- 2043 1451 36 (*) Integrated from 0.5 eV to 10 MeV. 2043 1451 37 2043 1451 38 MF=3 Neutron cross sections 2043 1451 39 Below 1 keV, constant elastic scattering cross sections and 2043 1451 40 1/v capturte cross sections were given. The thermal scattering2043 1451 41 and capture cross sections are the same as those of JENDL-3.3, 2043 1451 42 i.e., 2.9 b and 0.74 b, respectively. 2043 1451 43 2043 1451 44 The cross sections were calcualted /2/ by using the TNG code 2043 1451 45 /3/. The optilcal model parameters of Koning and Delaroche /4/2043 1451 46 were used for neutrons and protons. The alpha-particle 2043 1451 47 potential parameters were derived from the code developed by 2043 1451 48 Kumar and Kailas./5/ 2043 1451 49 2043 1451 50 MT= 1 Total 2043 1451 51 The cross sections were calculated with the TNG code./3/ 2043 1451 52 2043 1451 53 MT= 2 Elastic scattering 2043 1451 54 Obtained by subtracting the sum of the partial cross sections 2043 1451 55 from the total cross section. 2043 1451 56 2043 1451 57 MT= 4, 51-87, 91 Inelastic scattering 2043 1451 58 The cross sections were calculated with the TNG code./3/ 2043 1451 59 2043 1451 60 MT= 16 (n,2n) 2043 1451 61 The cross sections were calculated with the TNG code./3/ 2043 1451 62 2043 1451 63 MT= 17 (n,3n) 2043 1451 64 The cross sections were calculated with the TNG code./3/ 2043 1451 65 2043 1451 66 MT= 22 (n,na) 2043 1451 67 The cross sections were calculated with the TNG code./3/ 2043 1451 68 2043 1451 69 MT= 28 (n,np) 2043 1451 70 The cross sections were calculated with the TNG code./3/ 2043 1451 71 2043 1451 72 MT= 102 Capture 2043 1451 73 The cross sections were calculated with the TNG code./3/ 2043 1451 74 2043 1451 75 MT= 103 (n,p) 2043 1451 76 The cross sections were calculated with the TNG code./3/ 2043 1451 77 2043 1451 78 MT= 107 (n,a) 2043 1451 79 The cross sections were calculated with the TNG code./3/ 2043 1451 80 2043 1451 81 MT= 600-649 partial (n,p) cross sections 2043 1451 82 The cross sections were calculated with the TNG code./3/ 2043 1451 83 2043 1451 84 MT= 800-849 partial (n,a) cross sections 2043 1451 85 The cross sections were calculated with the TNG code./3/ 2043 1451 86 2043 1451 87 MF=4 Angular distributions of secondary neutrons 2043 1451 88 MT=2 2043 1451 89 Calculated with the TNG code/3/. 2043 1451 90 2043 1451 91 MF=6 Energy-angle distributions of secondary particles 2043 1451 92 MT= 16 (n,2n) reaction 2043 1451 93 Neutron and gamma-ray spectra calculated with TNG/3/. 2043 1451 94 2043 1451 95 MT= 17 (n,3n) reaction 2043 1451 96 Neutron and gamma-ray spectra calculated with TNG/3/. 2043 1451 97 2043 1451 98 MT= 22 (n,na) reaction 2043 1451 99 Neutron, alpha-particle, and gamma-ray spectra calculated with 2043 1451 100 TNG/3/. 2043 1451 101 2043 1451 102 MT= 28 (n,np) reaction 2043 1451 103 Neutron, proton, and gamma-ray spectra calculated with TNG/3/. 2043 1451 104 2043 1451 105 MT= 51-87 (n,n') reaction 2043 1451 106 Neutron angular distributions and discrete gamma-ray spectra 2043 1451 107 calculated with TNG/3/. 2043 1451 108 2043 1451 109 MT= 91 (n,n') reaction 2043 1451 110 Neutron spectra, and discrete-continuous gamma-ray spectra 2043 1451 111 calculated with with TNG/3/. 2043 1451 112 2043 1451 113 MT= 102 2043 1451 114 Calculated with the TNG code /3/. 2043 1451 115 2043 1451 116 MT= 600-608 (n,p) reactions leading to discrete levels 2043 1451 117 Proton angular distributions and discrete gamma-ray spectra 2043 1451 118 calculated with TNG/3/. 2043 1451 119 2043 1451 120 MT= 649 (n,p) reaction leading to continuum levels 2043 1451 121 Proton spectra and discrete-continuous gamma-ray spectra 2043 1451 122 calculated with TNG/3/. 2043 1451 123 2043 1451 124 MT= 800 (n,a) reactions leading to discrete levels 2043 1451 125 Alpha-particle angular distributions calculated with TNG/3/. 2043 1451 126 2043 1451 127 MT= 849 (n,a) reaction leading to continuum levels 2043 1451 128 Alpha-particle spectra calculated with TNG/3/. 2043 1451 129 2043 1451 130 < Appendix > 2043 1451 131 ******************************************************************2043 1451 132 * Nuclear Model Calcualtions with TNG Code /3/ *2043 1451 133 ******************************************************************2043 1451 134 The description of the model calculations is given in Ref.2. 2043 1451 135 2043 1451 136 < Optical model parameters > 2043 1451 137 Neutron and protons: 2043 1451 138 Koning and Delaroche /4/ 2043 1451 139 Alphas: 2043 1451 140 The potential parameters were obtained using the code developed 2043 1451 141 by Kumar and Kailas./5/ 2043 1451 142 2043 1451 143 < Level scheme of Ca- 46 > 2043 1451 144 ------------------------- 2043 1451 145 No. Ex(MeV) J PI 2043 1451 146 ------------------------- 2043 1451 147 0 0.00000 0 + 2043 1451 148 1 1.34600 2 + 2043 1451 149 2 2.42310 0 + 2043 1451 150 3 2.57470 4 + 2043 1451 151 4 2.97390 6 + 2043 1451 152 5 3.02260 2 + 2043 1451 153 6 3.61400 3 - 2043 1451 154 7 3.63890 2 + 2043 1451 155 8 3.85970 4 + 2043 1451 156 9 3.95200 2 - 2043 1451 157 10 3.98800 3 - 2043 1451 158 11 4.18450 5 - 2043 1451 159 12 4.26100 1 - 2043 1451 160 13 4.40700 3 - 2043 1451 161 14 4.43020 2 + 2043 1451 162 15 4.48940 4 + 2043 1451 163 16 4.72880 5 - 2043 1451 164 17 4.74490 4 + 2043 1451 165 18 4.75800 0 + 2043 1451 166 19 4.99470 4 + 2043 1451 167 20 5.01360 4 + 2043 1451 168 21 5.05100 4 + 2043 1451 169 22 5.15160 4 + 2043 1451 170 23 5.21800 2 - 2043 1451 171 24 5.25150 4 + 2043 1451 172 25 5.31700 0 + 2043 1451 173 26 5.37960 3 - 2043 1451 174 27 5.39200 3 - 2043 1451 175 28 5.41670 4 - 2043 1451 176 29 5.43670 4 + 2043 1451 177 30 5.47400 3 - 2043 1451 178 31 5.53670 4 + 2043 1451 179 32 5.60000 0 + 2043 1451 180 33 5.62800 0 + 2043 1451 181 34 5.63800 4 + 2043 1451 182 35 5.67900 1 - 2043 1451 183 36 5.69000 4 + 2043 1451 184 37 5.72200 5 + 2043 1451 185 2043 1451 186 The direct-reaction process was taken into account for the 1st 2043 1451 187 ans 6th levels by DWBA. 2043 1451 188 2043 1451 189 < Level density parameters > 2043 1451 190 Energy dependent parameters of Mengoni-Nakajima /6/ were used. 2043 1451 191 ---------------------------------------------------------- 2043 1451 192 Nuclei a* Pair Esh T E0 Ematch Econt 2043 1451 193 1/MeV MeV MeV MeV MeV MeV MeV 2043 1451 194 ---------------------------------------------------------- 2043 1451 195 Ca- 47 7.460 1.750 -0.360 0.759 3.034 7.442 4.386 2043 1451 196 Ca- 46 6.726 3.539 0.523 1.285 1.138 10.682 5.782 2043 1451 197 Ca- 45 7.212 1.789 0.882 1.223 -0.908 9.109 3.556 2043 1451 198 Ca- 44 6.485 3.618 1.143 1.463 -0.604 13.607 4.905 2043 1451 199 K - 46 6.734 0.000 0.257 0.478 3.317 5.761 3.383 2043 1451 200 K - 45 6.294 1.789 1.446 1.108 0.827 6.485 3.690 2043 1451 201 Ar- 43 6.962 1.830 1.898 0.757 1.830 3.485 1.830 2043 1451 202 Ar- 42 6.243 3.703 2.211 1.223 1.384 10.373 2.415 2043 1451 203 ---------------------------------------------------------- 2043 1451 204 2043 1451 205 References 2043 1451 206 1) Mughaghab S.F. et al.:"Neutron Cross Sections", Vol. 1, Part 2043 1451 207 A (1981). 2043 1451 208 2) Shibata, K: J. Nucl. Sci. Technol., 44, 10 (2007). 2043 1451 209 3) Fu, C.Y.: ORNL/TM-7042 (1980); Shibata, K., Fu, C.Y.: ORNL/TM-2043 1451 210 10093. 2043 1451 211 4) Koning, A.J., Delaroche, J.P.: Nucl. Phys., A713, 231 (2003). 2043 1451 212 5) Kumar, A., Kailas, S: a computer code contained in RIPL-2, 2043 1451 213 private communication (2002). 2043 1451 214 6) Mengoni, A., Nakajima, Y. Nucl. Sci. Technol., 31, 151 (1994).2043 1451 215 2043 1451 216 1 451 234 12043 1451 217 2 151 4 12043 1451 218 3 4 26 12043 1451 219 3 16 7 12043 1451 220 3 17 4 12043 1451 221 3 22 6 12043 1451 222 3 28 6 12043 1451 223 3 102 114 12043 1451 224 3 103 13 12043 1451 225 3 107 10 12043 1451 226 8 4 2 12043 1451 227 8 16 2 12043 1451 228 8 17 2 12043 1451 229 8 22 2 12043 1451 230 8 28 2 12043 1451 231 8 102 2 12043 1451 232 8 103 2 12043 1451 233 8 107 2 12043 1451 234 2043 1 099999 2043 0 0 0 2.004600+4 4.555890+1 0 0 1 02043 2151 1 2.004600+4 1.000000+0 0 0 1 02043 2151 2 1.000000-5 2.000000+7 0 0 0 02043 2151 3 0.000000+0 4.800000-1 0 0 0 02043 2151 4 2043 2 099999 2043 0 0 0 2.004600+4 4.555890+1 0 0 0 02043 3 4 1 0.000000+0-1.346000+6 0 0 1 672043 3 4 2 67 2 2043 3 4 3 1.375544+6 0.000000+0 1.500000+6 2.882206-1 2.000000+6 5.273540-12043 3 4 4 2.476286+6 6.396394-1 2.500000+6 6.689671-1 2.631214+6 6.901731-12043 3 4 5 3.000000+6 7.938610-1 3.039176+6 7.928788-1 3.088945+6 7.918149-12043 3 4 6 3.500000+6 9.268298-1 3.693326+6 9.101661-1 3.718772+6 9.123144-12043 3 4 7 3.944419+6 9.954391-1 4.000000+6 1.026743+0 4.038745+6 1.023808+02043 3 4 8 4.075535+6 1.025115+0 4.276348+6 1.052118+0 4.354528+6 1.063846+02043 3 4 9 4.500000+6 1.113323+0 4.503732+6 1.112964+0 4.527441+6 1.112239+02043 3 4 10 4.587940+6 1.116310+0 4.832596+6 1.144160+0 4.849048+6 1.146250+02043 3 4 11 4.862436+6 1.148976+0 5.000000+6 1.185188+0 5.104332+6 1.179360+02043 3 4 12 5.123646+6 1.178978+0 5.161868+6 1.179633+0 5.264676+6 1.185372+02043 3 4 13 5.332533+6 1.192305+0 5.366768+6 1.198521+0 5.433706+6 1.214931+02043 3 4 14 5.497680+6 1.234780+0 5.500000+6 1.237442+0 5.510352+6 1.236172+02043 3 4 15 5.535594+6 1.233899+0 5.556034+6 1.232497+0 5.594152+6 1.230889+02043 3 4 16 5.658228+6 1.230403+0 5.722918+6 1.231836+0 5.751532+6 1.233026+02043 3 4 17 5.761752+6 1.233662+0 5.803652+6 1.237776+0 5.814893+6 1.239459+02043 3 4 18 5.847596+6 1.245712+0 5.908504+6 1.258989+0 6.000000+6 1.290117+02043 3 4 19 6.500000+6 1.335265+0 7.000000+6 1.370781+0 7.500000+6 1.398264+02043 3 4 20 8.000000+6 1.400557+0 8.500000+6 1.388937+0 9.000000+6 1.370016+02043 3 4 21 9.500000+6 1.346767+0 1.000000+7 1.322435+0 1.100000+7 1.220518+02043 3 4 22 1.200000+7 9.473459-1 1.300000+7 6.757931-1 1.400000+7 4.808894-12043 3 4 23 1.450000+7 4.138487-1 1.500000+7 3.633594-1 1.600000+7 2.930228-12043 3 4 24 1.700000+7 2.476552-1 1.800000+7 2.160332-1 1.900000+7 1.924826-12043 3 4 25 2.000000+7 1.758668-1 2043 3 4 26 2043 3 099999 2.004600+4 4.555890+1 0 0 0 02043 3 16 1 -1.039400+7-1.039400+7 0 0 1 122043 3 16 2 12 2 2043 3 16 3 1.062214+7 0.000000+0 1.100000+7 5.851500-2 1.200000+7 2.948550-12043 3 16 4 1.300000+7 5.413000-1 1.400000+7 7.176000-1 1.450000+7 7.766000-12043 3 16 5 1.500000+7 8.191000-1 1.600000+7 8.723000-1 1.700000+7 8.974001-12043 3 16 6 1.800000+7 9.055001-1 1.900000+7 9.017848-1 2.000000+7 8.813210-12043 3 16 7 2043 3 099999 2.004600+4 4.555890+1 0 0 0 02043 3 17 1 -1.780900+7-1.780900+7 0 0 1 32043 3 17 2 3 2 2043 3 17 3 1.819990+7 0.000000+0 1.900000+7 1.015200-3 2.000000+7 1.102900-22043 3 17 4 2043 3 099999 2.004600+4 4.555890+1 0 0 0 02043 3 22 1 -1.113700+7-1.113700+7 0 0 1 92043 3 22 2 9 2 2043 3 22 3 1.138145+7 0.000000+0 1.400000+7 3.16570-10 1.450000+7 1.021600-82043 3 22 4 1.500000+7 4.354000-7 1.600000+7 2.889010-5 1.700000+7 2.764460-42043 3 22 5 1.800000+7 1.114110-3 1.900000+7 2.705150-3 2.000000+7 4.844820-32043 3 22 6 2043 3 099999 2.004600+4 4.555890+1 0 0 0 02043 3 28 1 -1.381600+7-1.381600+7 0 0 1 72043 3 28 2 7 2 2043 3 28 3 1.411926+7 0.000000+0 1.500000+7 1.094000-9 1.600000+7 5.603840-52043 3 28 4 1.700000+7 7.730280-4 1.800000+7 2.981500-3 1.900000+7 6.565750-32043 3 28 5 2.000000+7 1.092172-2 2043 3 28 6 2043 3 099999 2.004600+4 4.555890+1 0 0 0 02043 3102 1 7.276000+6 7.276000+6 0 0 1 3312043 3102 2 331 2 2043 3102 3 1.000000-5 3.722163+1 1.103037-5 3.544054+1 1.216691-5 3.374468+12043 3102 4 1.342055-5 3.212997+1 1.480336-5 3.059252+1 1.632865-5 2.912864+12043 3102 5 1.801111-5 2.773481+1 1.986691-5 2.640768+1 2.191394-5 2.514405+12043 3102 6 2.417189-5 2.394088+1 2.666248-5 2.279529+1 2.940971-5 2.170451+12043 3102 7 3.243999-5 2.066593+1 3.578251-5 1.967705+1 3.946943-5 1.873549+12043 3102 8 4.353624-5 1.783898+1 4.802208-5 1.698537+1 5.297013-5 1.617260+12043 3102 9 5.842801-5 1.539873+1 6.444825-5 1.466189+1 7.108881-5 1.396030+12043 3102 10 7.841358-5 1.329229+1 8.649308-5 1.265624+1 9.540506-5 1.205063+12043 3102 11 1.052353-4 1.147400+1 1.160784-4 1.092495+1 1.280388-4 1.040219+12043 3102 12 1.412315-4 9.904432+0 1.557836-4 9.430496+0 1.718351-4 8.979239+02043 3102 13 1.895404-4 8.549574+0 2.090701-4 8.140470+0 2.306120-4 7.750941+02043 3102 14 2.543736-4 7.380052+0 2.805835-4 7.026910+0 3.094939-4 6.690666+02043 3102 15 3.413832-4 6.370512+0 3.765583-4 6.065677+0 4.153577-4 5.775429+02043 3102 16 4.581549-4 5.499070+0 5.053618-4 5.235934+0 5.574328-4 4.985390+02043 3102 17 6.148689-4 4.746835+0 6.782232-4 4.519695+0 7.481052-4 4.303423+02043 3102 18 8.251877-4 4.097501+0 9.102125-4 3.901432+0 1.003998-3 3.714745+02043 3102 19 1.107447-3 3.536991+0 1.221555-3 3.367743+0 1.347420-3 3.206593+02043 3102 20 1.486254-3 3.053155+0 1.639393-3 2.907059+0 1.808311-3 2.767954+02043 3102 21 1.994634-3 2.635505+0 2.200155-3 2.509393+0 2.426853-3 2.389317+02043 3102 22 2.676908-3 2.274986+0 2.952729-3 2.166126+0 3.256969-3 2.062475+02043 3102 23 3.592557-3 1.963784+0 3.962723-3 1.869815+0 4.371030-3 1.780343+02043 3102 24 4.821407-3 1.695152+0 5.318191-3 1.614037+0 5.866161-3 1.536804+02043 3102 25 6.470592-3 1.463267+0 7.137302-3 1.393248+0 7.872708-3 1.326580+02043 3102 26 8.683888-3 1.263102+0 9.578649-3 1.202662+0 1.056560-2 1.145115+02043 3102 27 1.165425-2 1.090322+0 1.285507-2 1.038154+0 1.417962-2 9.884878-12043 3102 28 1.564064-2 9.412056-1 1.725221-2 8.961966-1 1.902982-2 8.533530-12043 3102 29 2.099059-2 8.125679-1 2.315340-2 7.737354-1 2.524188-2 7.410726-12043 3102 30 2.530000-2 7.402218-1 2.790683-2 7.048312-1 3.078227-2 6.711221-12043 3102 31 3.395398-2 6.390181-1 3.745250-2 6.084480-1 4.131149-2 5.793361-12043 3102 32 4.556810-2 5.516166-1 5.026329-2 5.252194-1 5.544227-2 5.000812-12043 3102 33 6.115487-2 4.761525-1 6.745608-2 4.533777-1 7.440655-2 4.316846-12043 3102 34 8.207318-2 4.110241-1 9.052975-2 3.913622-1 9.985766-2 3.726377-12043 3102 35 1.101467-1 3.547923-1 1.214959-1 3.378064-1 1.340144-1 3.216632-12043 3102 36 1.478229-1 3.062742-1 1.630541-1 2.916020-1 1.798547-1 2.776606-12043 3102 37 1.983864-1 2.643817-1 2.188275-1 2.517173-1 2.413748-1 2.396537-12043 3102 38 2.662453-1 2.282121-1 2.957501-1 2.165367-1 3.262233-1 2.061487-12043 3102 39 3.598363-1 1.963026-1 3.969127-1 1.868972-1 4.378094-1 1.779588-12043 3102 40 4.829199-1 1.694521-1 5.326785-1 1.613425-1 5.875641-1 1.536039-12043 3102 41 6.481049-1 1.462534-1 7.198912-1 1.388060-1 7.940666-1 1.321274-12043 3102 42 8.758848-1 1.258232-1 9.661333-1 1.198056-1 1.065681+0 1.140708-12043 3102 43 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