20-Ca- 43 JAEA EVAL-JUN06 K.Shibata DIST-DEC21 20091228 ----JENDL-5 MATERIAL 2034 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 06-06 Evaluated by K.Shibata. 09-12 Compiled by K.Shibata 21-11 revised by O.Iwamoto (MF8/MT4,16,17,22,28,102,103,107) added 21-11 above 20 MeV, JENDL-4.0/HE merged by O.Iwamoto 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 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 40 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. For JENDL-4.0, the parameters were updated by using the values obtained by Moxon et al./2/ Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 1.1334E+01 Elastic 5.1312E+00 n,gamma 6.2030E+00 4.3115E+00 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF=3 Neutron cross sections Below 40 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 /3/ by using the TNG code /4/. The optilcal model parameters of Koning and Delaroche /5/ were used for neutrons and protons. The alpha-particle potential parameters were derived from the code developed by Kumar and Kailas./6/ MT= 1 Total The cross sections were calculated with the TNG code./4/ 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./4/ MT= 16 (n,2n) The cross sections were calculated with the TNG code./4/ MT= 17 (n,3n) The cross sections were calculated with the TNG code./4/ MT= 22 (n,na) The cross sections were calculated with the TNG code./4/ MT= 28 (n,np) The cross sections were calculated with the TNG code./4/ MT= 102 Capture The cross sections were calculated with the TNG code./4/ MT= 103 (n,p) The cross sections were calculated with the TNG code./4/ The calculated cross sections were multiplied by 2.4 in order to reproduce measured data. MT= 107 (n,a) The cross sections were calculated with the TNG code./4/ MT= 600-649 partial (n,p) cross sections The cross sections were calculated with the TNG code./4/ The calculated cross sections were multiplied by 2.4 in order to reproduce measured total (n,p) data. MT= 800-849 partial (n,a) cross sections The cross sections were calculated with the TNG code./4/ MF=4 Angular distributions of secondary neutrons MT=2 Calculated with the TNG code/4/. MF=6 Energy-angle distributions of secondary particles MT= 16 (n,2n) reaction Neutron and gamma-ray spectra calculated with TNG/4/. MT= 17 (n,3n) reaction Neutron calculated with TNG/4/. Gamma-ray channel is not open. MT= 22 (n,na) reaction Neutron, alpha-particle, and gamma-ray spectra calculated with TNG/4/. MT= 28 (n,np) reaction Neutron, proton, and gamma-ray spectra calculated with TNG/4/. MT= 51-89 (n,n') reaction Neutron angular distributions and discrete gamma-ray spectra calculated with TNG/4/. MT= 91 (n,n') reaction Neutron spectra, and discrete-continuous gamma-ray spectra calculated with with TNG/4/. MT= 102 Calculated with the TNG code /4/. MT= 600-634 (n,p) reactions leading to discrete levels Proton angular distributions and discrete gamma-ray spectra calculated with TNG/4/. MT= 649 (n,p) reaction leading to continuum levels Proton spectra and discrete-continuous gamma-ray spectra calculated with TNG/4/. MT= 800-839 (n,a) reactions leading to discrete levels Alpha-particle angular distributions and gamma-ray spectra calculated with TNG/4/. MT= 849 (n,a) reaction leading to continuum levels Alpha-particle spectra and discrete-continuous gamma-ray spectra calculated with TNG/4/. < Appendix > ****************************************************************** * Nuclear Model Calcualtions with TNG Code /4/ * ****************************************************************** The description of the model calculations is given in Ref.3. < Optical model parameters > Neutron and protons: Koning and Delaroche /5/ Alphas: The potential parameters were obtained using the code developed by Kumar and Kailas./6/ < Level scheme of Ca- 43 > ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 7/2 - 1 0.37280 5/2 - 2 0.59340 3/2 - 3 0.99030 3/2 + 4 1.39450 5/2 + 5 1.67780 11/2 - 6 1.90180 7/2 + 7 1.93130 5/2 - 8 1.95740 1/2 + 9 2.04630 3/2 - 10 2.06730 7/2 - 11 2.09390 9/2 - 12 2.10270 3/2 - 13 2.22400 3/2 - 14 2.24900 9/2 - 15 2.27270 5/2 + 16 2.40980 9/2 + 17 2.52300 9/2 - 18 2.61100 1/2 - 19 2.67370 7/2 - 20 2.69690 5/2 + 21 2.75300 1/2 + 22 2.75400 15/2 - 23 2.76970 1/2 + 24 2.84570 9/2 + 25 2.87800 1/2 - 26 2.94320 3/2 - 27 2.95140 11/2 + 28 3.02860 5/2 + 29 3.04940 7/2 + 30 3.05050 11/2 - 31 3.07590 5/2 + 32 3.09610 1/2 - 33 3.09710 5/2 + 34 3.19630 7/2 + 35 3.27800 7/2 + 36 3.28570 3/2 - 37 3.31530 3/2 - 38 3.37130 13/2 + 39 3.37700 5/2 - The direct-reaction process was taken into account for the 5th, 7th, 9th, 10th, and 11th levels by DWBA. < Level density parameters > Energy dependent parameters of Mengoni-Nakajima /7/ were used. ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Econt 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- Ca- 44 6.485 3.618 1.143 1.463 -0.604 13.607 4.905 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 K - 43 6.062 1.830 2.010 1.410 -1.729 10.733 3.393 K - 42 6.253 0.000 1.255 1.396 -3.279 8.501 2.251 Ar- 40 5.998 3.795 1.822 1.464 -0.092 13.254 5.378 Ar- 39 6.455 1.922 1.140 1.228 -0.117 8.268 4.178 ---------------------------------------------------------- References 1) Mughaghab S.F. et al.:"Neutron Cross Sections", Vol. 1, Part A (1981). 2) Moxon, M.C. et al.: Phys. Rev., C48, 553 (1993). 3) Shibata, K: J. Nucl. Sci. Technol., 44, 10 (2007). 4) Fu, C.Y.: ORNL/TM-7042 (1980); Shibata, K., Fu, C.Y.: ORNL/TM- 10093. 5) Koning, A.J., Delaroche, J.P.: Nucl. Phys., A713, 231 (2003). 6) Kumar, A., Kailas, S: a computer code contained in RIPL-2, private communication (2002). 7) Mengoni, A., Nakajima, Y. Nucl. Sci. Technol., 31, 151 (1994).