20-Ca- 42 JAEA EVAL-JUN06 K.Shibata DIST-MAY10 20091228 ----JENDL-4.0 MATERIAL 2031 -----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 The resolved resonance region remains unchanged from JENDL-3.3. Resolved parameters for MLBW formula were given in the energy region from 1.0e-5 eV to 300 keV. Parameters were taken from the recommended data of BNL/1/ and the data for a negative resonance were added so as to reproduce the recommended thermal cross sections for capture and scatterng/1/. The scattering radius was assumed to be 3.6 fermi. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 1.9199E+00 Elastic 1.2369E+00 n,gamma 6.8308E-01 3.7692E-01 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF=3 Neutron cross sections Below 300 keV, zero background cross section was given and all the cross-section data are reproduced from the evaluated resolved resonance parameters with MLBW formula. 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, 51-89, 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= 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= 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= 51-89 (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= 600-639 (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= 800-830 (n,a) reactions leading to discrete levels Alpha-particle angular distributions and gamma-ray spectra calculated with TNG/3/. MT= 849 (n,a) reaction leading to continuum levels Alpha-particle spectra and discrete-continuous gamma-ray 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- 42 > ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 0 + 1 1.52470 2 + 2 1.83730 0 + 3 2.42420 2 + 4 2.75240 4 + 5 3.18930 6 + 6 3.25390 4 + 7 3.30000 0 + 8 3.39200 2 + 9 3.44700 3 - 10 3.65400 2 + 11 3.88500 1 - 12 3.95440 4 - 13 3.99970 3 - 14 4.04700 3 - 15 4.09970 5 - 16 4.11700 3 - 17 4.23200 1 - 18 4.35400 4 - 19 4.41800 3 - 20 4.44300 4 + 21 4.45200 2 + 22 4.50500 3 + 23 4.56700 2 - 24 4.69010 3 - 25 4.71500 4 + 26 4.75970 2 + 27 4.86600 2 + 28 4.89600 5 - 29 4.90400 3 - 30 4.94700 2 - 31 4.97100 3 - 32 5.01710 4 + 33 5.07500 2 - 34 5.15800 3 - 35 5.18800 3 + 36 5.21000 2 + 37 5.21500 4 - 38 5.32000 3 - 39 5.34500 0 + The direct-reaction process was taken into account for the 1st, 3rd, 4th, 9th, 20th, 24th, and 31st 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- 43 6.962 1.830 0.922 1.322 -1.548 10.316 3.419 Ca- 42 6.243 3.703 0.470 1.550 -0.451 13.961 5.357 Ca- 41 6.285 1.874 -0.149 1.397 -0.507 9.227 4.728 Ca- 40 5.998 3.795 -1.846 1.494 2.450 10.045 7.113 K - 42 6.253 0.000 1.255 1.396 -3.279 8.501 2.251 K - 41 5.828 1.874 1.299 1.617 -2.774 12.920 3.572 Ar- 39 6.455 1.922 1.140 1.228 -0.117 8.268 4.178 Ar- 38 5.752 3.893 0.184 1.501 1.229 11.878 6.824 ---------------------------------------------------------- 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).