11-Na- 23 EVAL-DEC21 F.Minato DIST-DEC21 20211208 ----JENDL-5 MATERIAL 1125 REVISION -----INCIDENT NEUTRON DATA ------ENDF- FORMAT History 2021-12 Evaluated with CCONE and AMUR codes by F.Minato 21-12 revised by O.Iwamoto (MF8/MT4) added (MF9/MT102) JENDL/AD-2017 adopted 21-12 above 20 MeV, JENDL-4.0/HE merged by O.Iwamoto 21-12 (MF6/MT5) recoil spectrum added by O.Iwamoto 21-12 (MF8/MT102) LMF corrected by O.Iwamoto MF= 1 General information MT=451 Descriptive data and directory Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 3.88955e+00 Elastic 3.35651e+00 n,gamma 5.31742e-01 2.95012e-01 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 2 Resonance parameters MT=151 Scattering radius only AP=0.123x(AWR)**(1/3)+0.08 MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /1/ above 1 MeV. Below 1 MeV, the cross sections are evaluated by the AMUR code in which the analysis was based on the R-matrix theory with Reich-Moore approximation for capture reaction. MT= 2 Elastic scattering cross section Calculated with CCONE code /1/ above 1 MeV. Below 1 MeV, the cross sections are evaluated by the AMUR code in which the analysis was based on the R-matrix theory with Reich-Moore approximation for capture reaction. MT= 3 Non-elastic cross section Calculated with CCONE code /1/. MT=4,51-91 (n,n') cross section Calculated with CCONE code /1/. Below 1 MeV, the cross section of MT=51 are evaluated by the AMUR code in which the analysis was based on the R-matrix theory with Reich-Moore approximation for capture reaction. The cross sections of MT=51-56 above 1 MeV are taken from experimental data /2/. MT= 16 (n,2n) cross section Calculated with CCONE code /1/. MT= 22 (n,na) cross section Calculated with CCONE code /1/. MT= 28 (n,np) cross section Calculated with CCONE code /1/. MT= 29 (n,n2a) cross section Calculated with CCONE code /1/. MT= 32 (n,nd) cross section Calculated with CCONE code /1/. MT= 33 (n,nt) cross section Calculated with CCONE code /1/. MT=102 Capture cross section Calculated with CCONE code /1/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /1/. Below 10 MeV, the cross sections are replaced by those of JENDL-4.0 /3/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /1/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /1/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /1/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /1/. MT=108 (n,2a) cross section Calculated with CCONE code /1/. MT=112 (n,pa) cross section Calculated with CCONE code /1/. MT=117 (n,da) cross section Calculated with CCONE code /1/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /1/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Calculated with CCONE code /1/. MT= 22 (n,na) reaction Calculated with CCONE code /1/. MT= 28 (n,np) reaction Calculated with CCONE code /1/. MT= 29 (n,n2a) reaction Calculated with CCONE code /1/. MT= 32 (n,nd) reaction Calculated with CCONE code /1/. MT= 33 (n,nt) reaction Calculated with CCONE code /1/. MT=51-91 (n,n') reaction Calculated with CCONE code /1/. MT=102 Capture reaction Calculated with CCONE code /1/. MT=108 (n,2a) reaction Calculated with CCONE code /1/. MT=112 (n,pa) reaction Calculated with CCONE code /1/. MT=117 (n,da) reaction Calculated with CCONE code /1/. MT=600-649 (n,p) reaction Calculated with CCONE code /1/. MT=650-699 (n,d) reaction Calculated with CCONE code /1/. MT=700-749 (n,t) reaction Calculated with CCONE code /1/. MT=750-799 (n,He3) reaction Calculated with CCONE code /1/. MT=800-849 (n,a) reaction Calculated with CCONE code /1/. MF= 8 Information on decay data MT= 4 (n,n') 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= 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=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. MF=33 Covariances of neutron cross sections MT=1,2,4,16,22,28: taken from JENDL-4.0 /3/. MT=29,32,33,79,104,105,106,108,112,117 are newly evaluated by using CCONE and KALMAN codes. MF=34 Covariances of angular distributions MT=2 Elastic scattering Taken from JENDL-4.0 /3/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : K.Shibata/4/ proton : F.G.Perey/5/ deuteron: folding OMP, A.J.Koning and J.P.Delaroche/6/ triton : folding OMP, A.J.Koning and J.P.Delaroche/6/ He-3 : folding OMP, A.J.Koning and J.P.Delaroche/6/ alpha : J.R.Huizenga and G.Igo/7/ * Level scheme of Na-23 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 3/2 + 1 0.439990 5/2 + 2 2.076010 7/2 + 3 2.390730 1/2 + 4 2.639850 1/2 - 5 2.703500 9/2 + 6 2.982060 3/2 + 7 3.677600 3/2 - 8 3.848070 5/2 - 9 3.914240 5/2 + 10 4.429640 1/2 + 11 4.774610 7/2 + 12 5.378570 5/2 + 13 5.534000 11/2 + 14 5.741750 5/2 + 15 5.766030 3/2 + 16 5.776000 5/2 + 17 5.926810 7/2 + 18 5.964420 3/2 - 19 6.042190 7/2 - 20 6.114900 11/2 + 21 6.194600 5/2 - 22 6.235400 9/2 + 23 6.307960 1/2 + 24 6.354510 9/2 - 25 6.577790 9/2 + 26 6.618000 5/2 + 27 6.735510 3/2 + 28 6.819610 5/2 - 29 6.867690 5/2 + ----------------------- * Level density parameters (Gilbert-Cameron model/8/) --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Na-24 2.748 0.000 -0.676 3.543 -13.207 28.065 1.512 Na-23 2.874 2.502 -0.947 3.624 -7.731 29.774 6.868 Na-22 2.380 0.000 -1.620 3.015 0.020 13.830 6.189 Ne-23 5.338 2.502 1.138 1.547 -0.563 11.070 2.517 Ne-22 3.967 5.117 0.716 2.183 0.693 17.771 9.324 Ne-21 3.827 2.619 -0.446 2.317 -1.267 16.996 8.782 Ne-20 3.685 5.367 -1.756 2.357 3.121 20.347 11.528 F-22 3.967 0.000 1.037 2.272 -5.556 13.830 2.990 F-21 3.827 2.619 2.195 1.828 0.090 10.516 5.787 F-20 4.607 0.000 0.270 1.918 -3.799 11.589 2.194 F-19 3.543 2.753 0.484 2.518 -2.574 17.998 5.107 --------------------------------------------------------- * Gamma-ray strength functions for Na-24 E1: standard lorentzian model(SLO) ER= 29.02 (MeV) EG= 5.00 (MeV) SIG= 58.73 (mb) ER= 13.50 (MeV) EG= 6.00 (MeV) SIG= 0.65 (mb) M1: standard lorentzian model(SLO) ER= 14.21 (MeV) EG= 6.00 (MeV) SIG= 4.00 (mb) E2: standard lorentzian model(SLO) ER= 21.84 (MeV) EG= 5.82 (MeV) SIG= 0.52 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) C.Rouki et al., J.NIM/A 672, 82 (2012). 3) K.Shibata et al., J.Nucl.Sci.Technol. 48, 1 (2012). 4) K.Shibata, J.Nucl.Sci.Technol, 39, 1065 (2002). 5) F.G.Perey, Phys. Rev. 131,745 (1963) 6) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 7) J.R.Huizenga and G.Igo, Nucl. Phys. 29,462 (1962) 8) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965)