20-Ca- 46 JAEA EVAL-JUN06 K.Shibata DIST-MAY10 20091228 ----JENDL-4.0 MATERIAL 2043 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 06-06 Evaluated by K.Shibata. 09-12 Compiled by K.Shibata MF=1 General information MT=451 Descriptive data and dictionary MF=2 Resonance parameters MT=151 Resolved resonance parameters No resonance parameters are given. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 3.6800E+00 Elastic 2.9325E+00 n,gamma 7.4023E-01 3.6492E-01 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF=3 Neutron cross sections Below 1 keV, constant elastic scattering cross sections and 1/v capturte cross sections were given. The thermal scattering and capture cross sections are the same as those of JENDL-3.3, i.e., 2.9 b and 0.74 b, respectively. The cross sections were calcualted /2/ by using the TNG code /3/. The optilcal model parameters of Koning and Delaroche /4/ were used for neutrons and protons. The alpha-particle potential parameters were derived from the code developed by Kumar and Kailas./5/ MT= 1 Total The cross sections were calculated with the TNG code./3/ MT= 2 Elastic scattering Obtained by subtracting the sum of the partial cross sections from the total cross section. MT= 4, 51-87, 91 Inelastic scattering The cross sections were calculated with the TNG code./3/ MT= 16 (n,2n) The cross sections were calculated with the TNG code./3/ MT= 17 (n,3n) The cross sections were calculated with the TNG code./3/ MT= 22 (n,na) The cross sections were calculated with the TNG code./3/ MT= 28 (n,np) The cross sections were calculated with the TNG code./3/ MT= 102 Capture The cross sections were calculated with the TNG code./3/ MT= 103 (n,p) The cross sections were calculated with the TNG code./3/ MT= 107 (n,a) The cross sections were calculated with the TNG code./3/ MT= 600-649 partial (n,p) cross sections The cross sections were calculated with the TNG code./3/ MT= 800-849 partial (n,a) cross sections The cross sections were calculated with the TNG code./3/ MF=4 Angular distributions of secondary neutrons MT=2 Calculated with the TNG code/3/. MF=6 Energy-angle distributions of secondary particles MT= 16 (n,2n) reaction Neutron and gamma-ray spectra calculated with TNG/3/. MT= 17 (n,3n) reaction Neutron and gamma-ray spectra calculated with TNG/3/. MT= 22 (n,na) reaction Neutron, alpha-particle, and gamma-ray spectra calculated with TNG/3/. MT= 28 (n,np) reaction Neutron, proton, and gamma-ray spectra calculated with TNG/3/. MT= 51-87 (n,n') reaction Neutron angular distributions and discrete gamma-ray spectra calculated with TNG/3/. MT= 91 (n,n') reaction Neutron spectra, and discrete-continuous gamma-ray spectra calculated with with TNG/3/. MT= 102 Calculated with the TNG code /3/. MT= 600-608 (n,p) reactions leading to discrete levels Proton angular distributions and discrete gamma-ray spectra calculated with TNG/3/. MT= 649 (n,p) reaction leading to continuum levels Proton spectra and discrete-continuous gamma-ray spectra calculated with TNG/3/. MT= 800 (n,a) reactions leading to discrete levels Alpha-particle angular distributions calculated with TNG/3/. MT= 849 (n,a) reaction leading to continuum levels Alpha-particle spectra calculated with TNG/3/. < Appendix > ****************************************************************** * Nuclear Model Calcualtions with TNG Code /3/ * ****************************************************************** The description of the model calculations is given in Ref.2. < Optical model parameters > Neutron and protons: Koning and Delaroche /4/ Alphas: The potential parameters were obtained using the code developed by Kumar and Kailas./5/ < Level scheme of Ca- 46 > ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 0 + 1 1.34600 2 + 2 2.42310 0 + 3 2.57470 4 + 4 2.97390 6 + 5 3.02260 2 + 6 3.61400 3 - 7 3.63890 2 + 8 3.85970 4 + 9 3.95200 2 - 10 3.98800 3 - 11 4.18450 5 - 12 4.26100 1 - 13 4.40700 3 - 14 4.43020 2 + 15 4.48940 4 + 16 4.72880 5 - 17 4.74490 4 + 18 4.75800 0 + 19 4.99470 4 + 20 5.01360 4 + 21 5.05100 4 + 22 5.15160 4 + 23 5.21800 2 - 24 5.25150 4 + 25 5.31700 0 + 26 5.37960 3 - 27 5.39200 3 - 28 5.41670 4 - 29 5.43670 4 + 30 5.47400 3 - 31 5.53670 4 + 32 5.60000 0 + 33 5.62800 0 + 34 5.63800 4 + 35 5.67900 1 - 36 5.69000 4 + 37 5.72200 5 + The direct-reaction process was taken into account for the 1st ans 6th levels by DWBA. < Level density parameters > Energy dependent parameters of Mengoni-Nakajima /6/ were used. ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Econt 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- Ca- 47 7.460 1.750 -0.360 0.759 3.034 7.442 4.386 Ca- 46 6.726 3.539 0.523 1.285 1.138 10.682 5.782 Ca- 45 7.212 1.789 0.882 1.223 -0.908 9.109 3.556 Ca- 44 6.485 3.618 1.143 1.463 -0.604 13.607 4.905 K - 46 6.734 0.000 0.257 0.478 3.317 5.761 3.383 K - 45 6.294 1.789 1.446 1.108 0.827 6.485 3.690 Ar- 43 6.962 1.830 1.898 0.757 1.830 3.485 1.830 Ar- 42 6.243 3.703 2.211 1.223 1.384 10.373 2.415 ---------------------------------------------------------- References 1) Mughaghab S.F. et al.:"Neutron Cross Sections", Vol. 1, Part A (1981). 2) Shibata, K: J. Nucl. Sci. Technol., 44, 10 (2007). 3) Fu, C.Y.: ORNL/TM-7042 (1980); Shibata, K., Fu, C.Y.: ORNL/TM- 10093. 4) Koning, A.J., Delaroche, J.P.: Nucl. Phys., A713, 231 (2003). 5) Kumar, A., Kailas, S: a computer code contained in RIPL-2, private communication (2002). 6) Mengoni, A., Nakajima, Y. Nucl. Sci. Technol., 31, 151 (1994).