18-Ar- 41 JAEA EVAL-NOV21 F.Minato DIST-DEC21 20211205 ----JENDL-5 MATERIAL 1840 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2021-11 Evaluated by F.Minato MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Scattering radius only AP=0.123x(AWR)**(1/3)+0.08 Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 3.74983E+00 Elastic 3.23362E+00 (n,g) 5.08758E-01 2.69265E-01 ---------------------------------------------------------- (*) Integrated from 0.5 eV MF= 3 Neutron cross sections MT= 1 Total cross section MT= 2 Elastic scattering cross section < 100 keV: Calculated with the random resonance generator code/1/ with a condition of 4pi R^2=3.17+/-0.1 b at En=2.53e-2 eV, where R=0.123*(AWR)**(1/3)+0.08. >=100 keV: Calculated with CCONE code /2/. MT= 4,51-91 (n,n') cross section Calculated with CCONE code /2/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /1/. MT= 16 (n,2n) cross section Calculated with CCONE code /2/. MT= 17 (n,3n) cross section Calculated with CCONE code /2/. MT= 22 (n,na) cross section Calculated with CCONE code /2/. MT= 24 (n,2na) cross section Calculated with CCONE code /2/. MT= 28 (n,np) cross section Calculated with CCONE code /2/. MT= 32 (n,nd) cross section Calculated with CCONE code /2/. MT= 33 (n,nt) cross section Calculated with CCONE code /2/. MT=102 Capture cross section < 100 keV: Calculated with the random resonance generator code/1/ with a condition of 5.10 +/- 0.02 at En=0.0253 eV /3/. >=100 keV: Calculated with CCONE code /2/. Direct and Semi-Direct components without the interference effect are also considered through the dcap code/4/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /2/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /2/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /2/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /2/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /2/. MT=108 (n,2a) cross section Calculated with CCONE code /2/. MT=111 (n,2p) cross section Calculated with CCONE code /2/. MT=112 (n,pa) cross section Calculated with CCONE code /2/. MT=155 (n,ta) cross section Calculated with CCONE code /2/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /2/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /2/. MT= 16 (n,2n) reaction Calculated with CCONE code /2/. MT= 17 (n,3n) reaction Calculated with CCONE code /2/. MT= 22 (n,na) reaction Calculated with CCONE code /2/. MT= 24 (n,2na) reaction Calculated with CCONE code /2/. MT= 28 (n,np) reaction Calculated with CCONE code /2/. MT= 32 (n,nd) reaction Calculated with CCONE code /2/. MT= 33 (n,nt) reaction Calculated with CCONE code /2/. MT=51-91 (n,n') reaction Calculated with CCONE code /2/. MT=102 Capture reaction Calculated with CCONE code /2/. MT=108 (n,2a) reaction Calculated with CCONE code /2/. MT=111 (n,2p) reaction Calculated with CCONE code /2/. MT=112 (n,pa) reaction Calculated with CCONE code /2/. MT=155 (n,ta) reaction Calculated with CCONE code /2/. MT=600-649 (n,p) reaction Calculated with CCONE code /2/. MT=650-699 (n,d) reaction Calculated with CCONE code /2/. MT=700-749 (n,t) reaction Calculated with CCONE code /2/. MT=750-799 (n,He3) reaction Calculated with CCONE code /2/. MT=800-849 (n,a) reaction Calculated with CCONE code /2/. MF= 8 Information on decay data MT= 4 (n,n') reaction Decay chain is given in the decay data file. MT= 5 Total reaction (except fission) reaction Decay chain is given in the decay data file. MT= 16 (n,2n) reaction Decay chain is given in the decay data file. MT= 17 (n,3n) reaction Decay chain is given in the decay data file. MT= 22 (n,na) reaction Decay chain is given in the decay data file. MT= 24 (n,2na) reaction Decay chain is given in the decay data file. MT= 28 (n,np) reaction Decay chain is given in the decay data file. MT= 32 (n,nd) reaction Decay chain is given in the decay data file. MT= 33 (n,nt) reaction Decay chain is given in the decay data file. MT=102 Capture reaction Decay chain is given in the decay data file. MT=103 (n,p) reaction Decay chain is given in the decay data file. MT=104 (n,d) reaction Decay chain is given in the decay data file. MT=105 (n,t) reaction Decay chain is given in the decay data file. MT=106 (n,He3) reaction Decay chain is given in the decay data file. MT=107 (n,a) reaction Decay chain is given in the decay data file. MT=108 (n,2a) reaction Decay chain is given in the decay data file. MT=111 (n,2p) reaction Decay chain is given in the decay data file. MT=112 (n,pa) reaction Decay chain is given in the decay data file. MT=155 (n,ta) reaction Decay chain is given in the decay data file. MF=10 Nuclide production cross sections MT= 33 (n,nt) reaction Calculated with CCONE code /2/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /2/ ------------------------------------------------------------------ * Optical model potentials neutron : A.J.Koning and J.P.Delaroche/5/ proton : global OMP, A.J.Koning and J.P.Delaroche/5/ deuteron: folding OMP, A.J.Koning and J.P.Delaroche/5/ triton : folding OMP, A.J.Koning and J.P.Delaroche/5/ He-3 : folding OMP, A.J.Koning and J.P.Delaroche/5/ alpha : E.D.Arthur and P.G.Young/6/ * Level scheme of Ar-41 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 7/2 - 1 0.167300 5/2 - 2 0.516000 3/2 - 3 1.034700 3/2 + 4 1.354000 3/2 - 5 1.636000 3/2 - 6 1.870000 1/2 + 7 1.988000 5/2 + 8 2.321000 5/2 + 9 2.398300 1/2 - 10 2.568000 1/2 + 11 2.701000 3/2 - 12 2.733400 3/2 - 13 2.891000 9/2 + 14 2.948500 3/2 - 15 3.009700 3/2 - 16 3.122000 3/2 + 17 3.293000 3/2 - 18 3.326700 1/2 - 19 3.388000 1/2 - 20 3.433000 1/2 - 21 3.485000 3/2 + 22 3.565000 1/2 + 23 3.590000 3/2 - 24 3.698000 3/2 + 25 3.734000 1/2 + 26 3.775000 3/2 + 27 3.799000 1/2 - 28 3.847000 3/2 + 29 3.900000 1/2 + 30 3.968200 1/2 - ----------------------- * Level density parameters (Gilbert-Cameron model/6/) Energy dependent parameters of Mengoni-Nakajima/7/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Ar-42 6.578 3.703 3.188 1.098 1.441 9.504 4.405 Ar-41 6.454 1.874 3.128 0.899 1.151 5.478 3.968 Ar-40 6.329 3.795 2.472 1.314 0.294 11.652 6.013 Ar-39 6.204 1.922 1.358 1.278 -0.380 8.852 3.893 Cl-41 6.454 1.874 3.563 1.377 -3.183 10.944 0.130 Cl-40 6.329 0.000 2.797 1.074 -1.636 5.146 0.212 Cl-39 7.445 1.922 2.837 0.937 0.271 6.702 2.586 Cl-38 6.078 0.000 0.872 1.351 -2.418 7.539 1.981 S-40 6.329 3.795 3.289 1.291 0.017 11.536 0.904 S-39 6.204 1.922 3.404 0.899 1.274 5.389 1.469 S-38 6.078 3.893 3.013 1.285 0.707 11.108 1.292 S-37 5.952 1.973 2.016 1.107 0.846 6.784 3.918 S-36 5.825 4.000 0.158 1.377 2.234 11.227 6.187 --------------------------------------------------------- * Gamma-ray strength functions for Ar-42 E1: enhanced generalized lorentzian model(EGLO)/8/ ER= 20.02 (MeV) EG= 7.96 (MeV) SIG= 59.24 (mb) M1: standard lorentzian model(SLO) ER= 11.80 (MeV) EG= 4.00 (MeV) SIG= 1.32 (mb) E2: standard lorentzian model(SLO) ER= 18.12 (MeV) EG= 5.61 (MeV) SIG= 0.82 (mb) References 1) N.Furutachi, F.Minato, O.Iwamoto, Phys. Rev. C 100, 014610 (2019) 2) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 3) S.F.Mughabghab et al., Neutron Cross Sections, 6th Edition. 4) F.Minato and T.Fukui, EPJ Web of Conf. 163, 00037 (2017) 5) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 6) E.D.Arthur and P.G.Young, Report LA-8636-MS(ENDF-304) (1980) 7) A.Gilbert and A.G.W.Cameron, Can. J. Phys, 43, 1446 (1965) 8) A.Mengoni and Y.Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 9) J.Kopecky et al., Phys. Rev. C 47, 312 (1993)