20-Ca- 40 JAEA EVAL-JUN06 K.Shibata DIST-DEC21 20091228 ----JENDL-5 MATERIAL 2025 -----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/MT16,22,28,102,103,107) JENDL/AD-2017 adopted (MF8/MT4) 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 500 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 3.4685E+00 Elastic 3.0610E+00 n,gamma 4.0760E-01 2.1274E-01 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF=3 Neutron cross sections Below 500 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 total cross section was taken from the JENDL-3.3 evaluation that was based on the experimental data of Cierjacks et al./6/ and Foster, Jr. and Glasgow /7/. MT= 2 Elastic scattering Obtained by subtracting the sum of the partial cross sections from the total cross section. MT= 4, 51-73, 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= 51-73 (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= 800-832 (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- 40 > ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 0 + 1 3.35260 0 + 2 3.73670 3 - 3 3.90440 2 + 4 4.49140 5 - 5 5.21160 0 + 6 5.24880 2 + 7 5.27880 4 + 8 5.61350 4 - 9 5.62940 2 + 10 5.90260 1 - 11 6.02550 2 - 12 6.02970 3 + 13 6.28520 3 - 14 6.42240 2 + 15 6.50790 4 + 16 6.54280 4 + 17 6.58250 3 - 18 6.75040 2 - 19 6.90870 2 + 20 6.93020 6 + 21 6.93130 3 - 22 6.93800 3 - 23 6.95050 1 - The direct-reaction process was taken into account for the 2nd, 3rd, 4th, 6th, 7th, 9th, 13th, 14th, 15th, 17th, and 19th levels by DWBA. < Level density parameters > Energy dependent parameters of Mengoni-Nakajima /8/ were used. ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Econt 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- 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 Ca- 39 6.455 1.922 -0.346 0.839 3.517 8.268 4.920 K - 40 6.010 0.000 -0.027 1.352 -1.491 6.250 3.557 K - 39 5.593 1.922 -0.694 1.476 0.637 8.268 5.502 Ar- 37 6.197 1.973 -0.393 1.348 0.521 8.189 5.213 Ar- 36 5.504 4.000 -1.321 1.645 1.856 11.777 7.423 ---------------------------------------------------------- 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) Cierjacks, S. et al.: KFK-1000 (1968). 7) Foster, D.G, Glasgow, D.W.: Phys. Rev. C3, 576 (1971). 8) Mengoni, A., Nakajima, Y. Nucl. Sci. Technol., 31, 151 (1994).