18-Ar- 37 JAEA EVAL-DEC21 F.Minato DIST-DEC21 20211210 ----JENDL-5 MATERIAL 1828 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2021-08 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 1.11359E+03 Elastic 1.32461E+00 (n,g) 1.48613E+00 2.19990E+00 (n,p) 3.71754E+01 (n,a) 1.07358E+03 ---------------------------------------------------------- (*) Integrated from 0.5 eV MF= 3 Neutron cross sections MT= 1 Total cross section Resolved resonance region (MLBW formula) : below 4 keV The resonance energies, neutron widths and radiation width were based on the Mughabghab/1/. Calculated with CCONE code /2/ above 4 keV. MT= 2 Elastic scattering cross section Resolved resonance region (MLBW formula) : below 4 keV The resonance energies, neutron widths and radiation width were based on the Mughabghab/1/. Calculated with CCONE code /2/ above 4 keV. 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 /2/. MT= 16 (n,2n) 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= 29 (n,n2a) cross section Calculated with CCONE code /2/. MT= 32 (n,nd) cross section Calculated with CCONE code /2/. MT= 34 (n,nHe3) cross section Calculated with CCONE code /2/. MT= 41 (n,2np) cross section Calculated with CCONE code /2/. MT= 44 (n,n2p) cross section Calculated with CCONE code /2/. MT= 45 (n,npa) cross section Calculated with CCONE code /2/. MT=102 Capture cross section < 4 keV: Resonance parameters from Mughabghab/1/. >= 4 keV: Calculated with CCONE code /2/. MT=103,600-649 (n,p) cross section < 4 keV: Calculated so as to reproduce Biebber+('99) experimental data. >= 4 keV: 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 < 4 keV: Calculated so as to reproduce Goeminne+('00) experimental data. >= 4 keV: Calculated with CCONE code /2/. MT=108 (n,2a) cross section Calculated with CCONE code /2/. MT=109 (n,3a) 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=115 (n,pd) cross section Calculated with CCONE code /2/. MT=116 (n,pt) cross section Calculated with CCONE code /2/. MT=117 (n,da) cross section Calculated with CCONE code /2/. MT=155 (n,ta) cross section Calculated with CCONE code /2/. MT=193 (n,He3a) 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= 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= 29 (n,n2a) reaction Calculated with CCONE code /2/. MT= 32 (n,nd) reaction Calculated with CCONE code /2/. MT= 34 (n,nHe3) reaction Calculated with CCONE code /2/. MT= 41 (n,2np) reaction Calculated with CCONE code /2/. MT= 44 (n,n2p) reaction Calculated with CCONE code /2/. MT= 45 (n,npa) 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=109 (n,3a) 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=115 (n,pd) reaction Calculated with CCONE code /2/. MT=116 (n,pt) reaction Calculated with CCONE code /2/. MT=117 (n,da) reaction Calculated with CCONE code /2/. MT=155 (n,ta) reaction Calculated with CCONE code /2/. MT=193 (n,He3a) 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= 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= 29 (n,n2a) 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= 34 (n,nHe3) reaction Decay chain is given in the decay data file. MT= 41 (n,2np) reaction Decay chain is given in the decay data file. MT= 44 (n,n2p) reaction Decay chain is given in the decay data file. MT= 45 (n,npa) 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=109 (n,3a) 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=115 (n,pd) reaction Decay chain is given in the decay data file. MT=116 (n,pt) reaction Decay chain is given in the decay data file. MT=117 (n,da) reaction Decay chain is given in the decay data file. MT=155 (n,ta) reaction Decay chain is given in the decay data file. MT=193 (n,He3a) reaction Decay chain is given in the decay data file. ------------------------------------------------------------------ nuclear model calculation with CCONE code /2/ ------------------------------------------------------------------ * Optical model potentials neutron : A.J.Koning and J.P.Delaroche/3/ proton : global OMP, A.J.Koning and J.P.Delaroche/3/ deuteron: folding OMP, A.J.Koning and J.P.Delaroche/3/ triton : folding OMP, A.J.Koning and J.P.Delaroche/3/ He-3 : folding OMP, A.J.Koning and J.P.Delaroche/3/ alpha : E.D.Arthur and P.G.Young/4/ * Level scheme of Ar-37 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 3/2 + 1 1.409840 1/2 + 2 1.611280 7/2 - 3 2.217000 7/2 + 4 2.490170 3/2 - 5 2.796150 5/2 + 6 3.170000 5/2 + 7 3.184740 9/2 - 8 3.273580 5/2 - 9 3.518100 3/2 - 10 3.526760 7/2 - 11 3.601800 3/2 + 12 3.706190 11/2 - 13 3.751000 7/2 + 14 3.900000 3/2 + 15 3.937100 3/2 + 16 3.981200 3/2 - 17 4.021600 9/2 - 18 4.193000 1/2 + 19 4.283870 7/2 + 20 4.320000 7/2 + 21 4.396700 5/2 - 22 4.444500 1/2 - 23 4.573400 5/2 + 24 4.624400 7/2 + 25 4.634800 3/2 - 26 4.729000 1/2 + 27 4.743400 7/2 + 28 4.755000 3/2 - 29 4.798800 5/2 - 30 4.830000 5/2 + 31 4.886500 7/2 + 32 4.981000 7/2 - ----------------------- * Level density parameters (Gilbert-Cameron model/5/) Energy dependent parameters of Mengoni-Nakajima/6/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Ar-38 6.078 3.893 -0.301 1.459 1.392 12.761 7.629 Ar-37 6.547 1.973 -1.140 1.327 0.504 9.582 4.981 Ar-36 5.825 4.000 -2.322 1.850 0.062 18.995 6.136 Cl-37 5.952 1.973 -0.263 1.257 1.141 7.711 6.305 Cl-36 5.825 0.000 -1.639 1.397 -0.618 7.016 4.497 Cl-35 5.698 2.028 -1.964 1.753 -0.965 14.347 5.010 S-36 5.825 4.000 0.158 1.377 2.234 11.227 6.187 S-35 5.698 2.028 -0.580 1.296 1.462 7.698 5.752 S-34 5.569 4.116 -1.359 1.798 0.363 16.662 6.954 S-33 5.441 2.089 -2.399 1.903 -1.361 16.738 5.711 S-32 7.435 4.243 -3.372 1.358 3.265 14.479 10.493 --------------------------------------------------------- * Gamma-ray strength functions for Ar-38 E1: enhanced generalized lorentzian model(EGLO)/7/ ER= 20.51 (MeV) EG= 8.34 (MeV) SIG= 52.09 (mb) M1: standard lorentzian model(SLO) ER= 12.20 (MeV) EG= 4.00 (MeV) SIG= 1.43 (mb) E2: standard lorentzian model(SLO) ER= 18.74 (MeV) EG= 5.65 (MeV) SIG= 0.90 (mb) References 1) S.F.Mughabghab et al., Neutron Cross Sections, 6th edition. 2) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 3) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 4) E.D.Arthur and P.G.Young, Report LA-8636-MS(ENDF-304) (1980) 5) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) 6) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 7) J. Kopecky et al., Phys. Rev. C 47, 312 (1993)