11-Na- 22 JAEA EVAL-SEP21 F.Minato DIST-DEC21 20211209 ----JENDL-5 MATERIAL 1122 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2021-10 Evaluated by F.Minato MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved resonance parameters Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 2.78903e+04 Elastic 7.55587e+01 n,gamma 4.12520e+01 3.35198e+01 n,p 2.74840e+04 1.37409e+04 n,alpha 2.62092e+02 1.25951e+02 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Sum of other cross sections. MT= 2 Elastic scattering cross section Resolved resonance region (MLBW formula) : below 10 keV The resonance energies, neutron widths and radiation widths were based on the Mughabghab/1/. Some modifications are performed for the gamma width to reproduce the thermal cap- ture cross section of 41.2 b determined by /2/. Calculated with CCONE code /3/ above 10 keV. MT=4,51-91 (n,n') cross section Calculated with CCONE code /3/. MT= 16 (n,2n) cross section Calculated with CCONE code /3/. MT= 22 (n,na) cross section Calculated with CCONE code /3/. MT= 24 (n,2na) cross section Calculated with CCONE code /3/. MT= 28 (n,np) cross section Calculated with CCONE code /3/. MT= 29 (n,n2a) cross section Calculated with CCONE code /3/. MT= 32 (n,nd) cross section Calculated with CCONE code /3/. MT= 41 (n,2np) cross section Calculated with CCONE code /3/. MT= 45 (n,npa) cross section Calculated with CCONE code /3/. MT=102 Capture cross section < 10 keV: Calculated with the random resonance generator code/1/ with a condition of 41.236 b at En=0.0253 eV, which is calculated from /2/. >=10 keV: Calculated with CCONE code /3/. 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 < 10 keV: Calculated with the resonance parameters /1/. >=10 keV: Calculated with CCONE code /3/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /3/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /3/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /3/. MT=107,800-849 (n,a) cross section < 10 keV: Calculated with the resonance parameters /1/. Some modifications are performed to repro- duce 262 b at En=0.0253 eV /1/. >=10 keV: Calculated with CCONE code /3/. MT=108 (n,2a) cross section Calculated with CCONE code /3/. MT=111 (n,2p) cross section Calculated with CCONE code /3/. MT=112 (n,pa) cross section Calculated with CCONE code /3/. MT=113 (n,t2a) cross section Calculated with CCONE code /3/. MT=115 (n,pd) cross section Calculated with CCONE code /3/. MT=117 (n,da) cross section Calculated with CCONE code /3/. MT=155 (n,ta) cross section Calculated with CCONE code /3/. MT=158 (n,nda) cross section Calculated with CCONE code /3/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /3/. 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 /3/. MT= 22 (n,na) reaction Calculated with CCONE code /3/. MT= 24 (n,2na) reaction Calculated with CCONE code /3/. MT= 28 (n,np) reaction Calculated with CCONE code /3/. MT= 29 (n,n2a) reaction Calculated with CCONE code /3/. MT= 32 (n,nd) reaction Calculated with CCONE code /3/. MT= 41 (n,2np) reaction Calculated with CCONE code /3/. MT= 45 (n,npa) reaction Calculated with CCONE code /3/. MT=51-91 (n,n') reaction Calculated with CCONE code /3/. MT=102 Capture reaction Calculated with CCONE code /3/. MT=108 (n,2a) reaction Calculated with CCONE code /3/. MT=111 (n,2p) reaction Calculated with CCONE code /3/. MT=112 (n,pa) reaction Calculated with CCONE code /3/. MT=113 (n,t2a) reaction Calculated with CCONE code /3/. MT=115 (n,pd) reaction Calculated with CCONE code /3/. MT=117 (n,da) reaction Calculated with CCONE code /3/. MT=155 (n,ta) reaction Calculated with CCONE code /3/. MT=158 (n,nda) reaction Calculated with CCONE code /3/. MT=600-649 (n,p) reaction Calculated with CCONE code /3/. MT=650-699 (n,d) reaction Calculated with CCONE code /3/. MT=700-749 (n,t) reaction Calculated with CCONE code /3/. MT=750-799 (n,He3) reaction Calculated with CCONE code /3/. MT=800-849 (n,a) reaction Calculated with CCONE code /3/. 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= 41 (n,2np) 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=113 (n,t2a) 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=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=158 (n,nda) reaction Decay chain is given in the decay data file. ------------------------------------------------------------------ nuclear model calculation with CCONE code /3/ ------------------------------------------------------------------ * Optical model potentials neutron : K.Shibata/5/ proton : F.G.Perey/6/ deuteron: folding OMP, A.J.Koning and J.P.Delaroche/7/ triton : folding OMP, A.J.Koning and J.P.Delaroche/7/ He-3 : folding OMP, A.J.Koning and J.P.Delaroche/7/ alpha : J.R.Huizenga and G.Igo/8/ * Level scheme of Na-22 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 3 + 1 0.583110 1 + 2 0.657160 0 + 3 0.890810 4 + 4 1.528140 5 + 5 1.936450 1 + 6 1.952130 2 + 7 1.983360 3 + 8 2.211630 1 - 9 2.571700 2 - 10 2.969000 3 + 11 3.060370 2 + 12 3.519670 3 - 13 3.706900 6 + 14 3.944400 1 + 15 4.071560 4 + 16 4.296200 0 - 17 4.319700 1 + 18 4.360570 2 + 19 4.468500 4 - 20 4.523900 5 + 21 4.582800 2 - 22 4.622000 1 - 23 4.710400 5 + 24 4.771000 3 + 25 5.063000 2 + 26 5.100900 4 + 27 5.131000 3 - 28 5.174000 1 + 29 5.318000 3 + 30 5.442000 2 - 31 5.603000 2 + 32 5.700000 0 + 33 5.725000 0 + 34 5.739000 1 + 35 5.832000 4 - 36 5.863000 1 + 37 5.920000 0 - 38 5.959000 2 - 39 5.988000 2 - 40 5.995000 2 + ----------------------- * Level density parameters (Gilbert-Cameron model/9/) Energy dependent parameters of Mengoni-Nakajima/10/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- 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 Na-21 3.827 2.619 -0.363 2.251 -0.777 15.921 6.468 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-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 F-18 3.398 0.000 -1.963 2.544 -2.213 16.386 9.020 F-17 3.252 2.910 -2.127 2.650 0.784 20.123 9.920 --------------------------------------------------------- * Gamma-ray strength functions for Na-23 E1: enhanced generalized lorentzian model(EGLO)/11/ ER= 18.44 (MeV) EG= 6.80 (MeV) SIG= 8.33 (mb) ER= 26.60 (MeV) EG= 13.70 (MeV) SIG= 16.65 (mb) M1: standard lorentzian model(SLO) ER= 14.42 (MeV) EG= 4.00 (MeV) SIG= 2.03 (mb) E2: standard lorentzian model(SLO) ER= 22.15 (MeV) EG= 5.83 (MeV) SIG= 0.54 (mb) References 1) S.F.Mughabghab et al., Neutron Cross Sections, 6th edition. 2) K.Shibata, J. 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