20-Ca- 44 JAEA EVAL-JUN06 K.Shibata DIST-MAY10 20091228 ----JENDL-4.0 MATERIAL 2037 -----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 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 4.2473E+00 Elastic 3.3587E+00 n,gamma 8.8863E-01 4.2453E-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 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= 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 calculated with TNG/3/. Gamma-ray channel is not open. 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= 600-603 (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= 800-829 (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- 44 > ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 0 + 1 1.15710 2 + 2 1.88350 0 + 3 2.28310 4 + 4 2.65650 2 + 5 3.04430 4 + 6 3.28500 6 + 7 3.30130 2 + 8 3.30790 3 - 9 3.35720 3 + 10 3.58040 3 + 11 3.66150 1 - 12 3.67610 2 - 13 3.71180 4 - 14 3.77620 2 + 15 3.86500 5 - 16 3.91350 5 - 17 3.92260 3 + 18 4.01140 3 + 19 4.09200 2 + 20 4.16900 1 + 21 4.19570 2 + 22 4.26020 3 + 23 4.31520 3 + 24 4.35840 3 - 25 4.39940 3 - 26 4.40920 1 - 27 4.43700 2 + 28 4.47980 2 + 29 4.55260 1 - 30 4.56490 5 - 31 4.57300 3 - 32 4.58410 3 + 33 4.60400 1 + 34 4.65100 2 + 35 4.69020 2 + 36 4.80370 1 - 37 4.82400 2 - 38 4.86610 2 + 39 4.88400 2 - The direct-reaction process was taken into account for the 1st, 3rd, 4th, 8th, 16th, and 25th 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- 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 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 K - 44 6.494 0.000 1.303 1.184 -1.660 5.909 0.812 K - 43 6.062 1.830 2.010 1.410 -1.729 10.733 3.393 Ar- 41 8.342 1.874 2.006 0.721 1.512 4.471 3.968 Ar- 40 5.998 3.795 1.822 1.464 -0.092 13.254 5.378 ---------------------------------------------------------- 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).