10-Ne- 20 JAEA EVAL-Jul19 N.Iwamoto,F.Minato DIST-DEC21 20190725 ----JENDL-5 MATERIAL 1025 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2020-09 Evaluated with CCONE code by N.Iwamoto 21-11 revised by O.Iwamoto (MF8/MT4) added 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved and unresolved resonance parameters Resolved resonance region (R-M formula) : below 2.3 MeV Adopted resonance paramters were retrieved from Cohn et al./1/, Heil et al./2/ and Mughabghab /3/. The thermal capture cross section was taken from Bellmann/4/. The direct and semi-direct capture cross sections were added in the energy region of 1e-5eV to 20MeV/5/. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 2.5786E+00 Elastic 2.5418E+00 n,gamma 3.6802E-02 1.6901E-02 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /6/. MT= 2 Elastic scattering cross section Obtained by subtracting the sum of the partial cross sections from the total cross section. MT= 4,51-91 (n,n') cross section Calculated with CCONE code /6/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /6/. MT= 16 (n,2n) cross section Calculated with CCONE code /6/. MT= 22 (n,na) cross section Calculated with CCONE code /6/. MT= 28 (n,np) cross section Calculated with CCONE code /6/. MT= 29 (n,n2a) cross section Calculated with CCONE code /6/. MT= 45 (n,npa) cross section Calculated with CCONE code /6/. MT=102 Capture cross section Calculated with CCONE code /6/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /6/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /6/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /6/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /6/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /6/. MT=108 (n,2a) cross section Calculated with CCONE code /6/. MT=111 (n,2p) cross section Calculated with CCONE code /6/. MT=112 (n,pa) cross section Calculated with CCONE code /6/. MT=117 (n,da) cross section Calculated with CCONE code /6/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /6/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /1/. MT= 16 (n,2n) reaction Calculated with CCONE code /6/. MT= 22 (n,na) reaction Calculated with CCONE code /6/. MT= 28 (n,np) reaction Calculated with CCONE code /6/. MT= 29 (n,n2a) reaction Calculated with CCONE code /6/. MT= 45 (n,npa) reaction Calculated with CCONE code /6/. MT=51-91 (n,n') reaction Calculated with CCONE code /6/. MT=102 Capture reaction Calculated with CCONE code /6/. MT=108 (n,2a) reaction Calculated with CCONE code /6/. MT=111 (n,2p) reaction Calculated with CCONE code /6/. MT=112 (n,pa) reaction Calculated with CCONE code /6/. MT=117 (n,da) reaction Calculated with CCONE code /6/. MT=600-649 (n,p) reaction Calculated with CCONE code /6/. MT=650-699 (n,d) reaction Calculated with CCONE code /6/. MT=700-749 (n,t) reaction Calculated with CCONE code /6/. MT=750-799 (n,He3) reaction Calculated with CCONE code /6/. MT=800-849 (n,a) reaction Calculated with CCONE code /6/. 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= 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= 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=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=117 (n,da) reaction Decay chain is given in the decay data file. ------------------------------------------------------------------ nuclear model calculation with CCONE code /6/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al./7/ modified proton : global OMP, A.J.Koning and J.P.Delaroche/8/ deuteron: Y.Han et al./9/ triton : folding OMP, A.J.Koning and J.P.Delaroche/8/ He-3 : Y.Xu et al./10/ alpha : V.Avrigeanu/11/ * Level scheme of Ne-20 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 1.633670 2 + 2 4.247700 4 + 3 4.966510 2 - 4 5.621400 3 - 5 5.787700 1 - 6 6.706000 3 - 7 6.725000 0 + 8 7.004000 4 - 9 7.156300 3 - 10 7.191000 0 + 11 7.421900 2 + 12 7.833400 2 + 13 8.453000 5 - 14 8.700000 0 + 15 8.708000 1 - 16 8.777600 6 + 17 8.820000 5 - 18 8.854000 1 - 19 9.000000 2 + 20 9.031000 4 + 21 9.116000 3 - 22 9.196000 2 + 23 9.318000 2 - 24 9.487000 2 + 25 9.873000 3 + 26 9.935000 1 + 27 9.990000 4 + 28 10.262000 5 - 29 10.273200 2 + 30 10.406000 3 - 31 10.553000 4 + 32 10.584000 2 + 33 10.609000 6 - 34 10.694000 3 + 35 10.800000 4 + 36 10.840000 3 - 37 10.843000 2 + 38 10.884000 3 + 39 10.917000 3 + 40 10.940000 2 + ----------------------- * Level density parameters (Gilbert-Cameron model/12/) Energy dependent parameters of Mengoni-Nakajima/13/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Ne-21 4.017 2.619 -0.446 2.207 -1.067 16.300 7.211 Ne-20 4.110 5.367 -1.756 2.181 2.912 19.862 10.940 Ne-19 3.723 2.753 0.612 2.222 -0.961 14.760 6.437 F-20 4.136 0.000 0.270 1.806 -1.648 8.389 5.067 F-19 3.119 2.753 0.484 3.048 -5.062 22.976 6.989 F-18 3.647 0.000 -1.963 2.439 -2.533 16.386 6.567 O-19 3.723 2.753 1.432 2.124 -0.961 13.372 5.705 O-18 3.149 5.657 0.873 2.819 -0.585 22.305 9.270 O-17 3.765 2.910 -2.141 2.428 0.119 20.123 9.194 O-16 2.868 6.000 -5.253 3.446 2.552 36.870 14.302 --------------------------------------------------------- * Gamma-ray strength functions for Ne-21 E1: hybrid model(GH)/14/ ER= 19.00 (MeV) EG= 7.20 (MeV) SIG= 7.28 (mb) ER= 27.06 (MeV) EG= 14.15 (MeV) SIG= 14.56 (mb) M1: standard lorentzian model(SLO) ER= 14.86 (MeV) EG= 4.00 (MeV) SIG= 4.25 (mb) E2: standard lorentzian model(SLO) ER= 22.83 (MeV) EG= 5.86 (MeV) SIG= 0.48 (mb) References 1) H.O.Cohn and J.L.Fowler, Phys. Rev. 114, 194 (1959) 2) M.Heil et al., Phys. Rev. C90, 045804 (2014) 3) S.F.Mughabghab, Atlas of Neutron Resonances: Resonance Parameters and Thermal Cross Sections (2006) 4) D.Bellmann, Atomkernenergie, Vol.17, p.145 (1971) 5) F.Minato and T.Fukui, EPJ Web of Conferences, 163, 00037 (2017) 6) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 7) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 8) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 9) Y.Han et al., Phys. Rev. C74,044615(2006) 10) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54, 2005 (2011) 11) V.Avrigeanu, Phys. Rev. C82, 014606 (2010) 12) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) 13) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 14) S. Goriely, Phys. Lett. B436, 10 (1998)