13-Al- 26 JAEA EVAL-Nov21 N.Iwamoto DIST-DEC21 20211111 ----JENDL-5 MATERIAL 1322 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-09 Evaluated with CCONE code by N.Iwamoto 21-10 JENDL-5rc1 revised by N.Iwamoto (MF2/MT151) revised (MF3/MT103,107,600-649,800-849) revised 21-12 JENDL-5rc1 revised by N.Iwamoto (MF2/MT151) Changed (MF3/1,2,102) Reconstructed from RP. MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Scattering radius only AP is assumed to be 5.00 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 6.53876E+00 Elastic 3.21182E+00 n,gamma 7.00982E-02 6.17518E-01 n,p 2.38033E+00 1.64305E+00 n,alpha 8.75405E-01 9.44201E-01 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Resolved resonance parameters were based on the data of de Smet et al./1/. The paramters were adjusted so as to reproduce the measured resonance cross sections as well as thermal ones, taking into account a negative resonance. Calculated with CCONE code /2/. MT= 2 Elastic scattering cross section 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 /2/. MT= 16 (n,2n) cross section Calculated with CCONE code /2/. MT= 22 (n,na) 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= 41 (n,2np) cross section Calculated with CCONE code /2/. MT=102 Capture cross section Calculated with CCONE code /2/. 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=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/. 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= 28 (n,np) reaction Calculated with CCONE code /2/. MT= 32 (n,nd) reaction Calculated with CCONE code /2/. MT= 41 (n,2np) 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=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=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= 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= 41 (n,2np) 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=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. MF=10 Nuclide production reactions MT= 4 (n,n') reaction Calculated with CCONE code /2/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /2/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al./3/ proton : global OMP, A.J.Koning and J.P.Delaroche/4/ deuteron: Y.Han et al./5/ triton : folding OMP, A.J.Koning and J.P.Delaroche/4/ He-3 : Y.Xu et al./6/ alpha : M.Avrigeanu and V.Avrigeanu/7/ * Level scheme of Al-26 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 5 + 1 0.228310 0 + 2 0.416850 3 + 3 1.057740 1 + 4 1.759030 2 + 5 1.850620 1 + 6 2.068860 4 + 7 2.069470 2 + 8 2.071640 1 + 9 2.365150 3 + 10 2.545370 3 + 11 2.660920 2 + 12 2.740030 1 + 13 2.913400 2 + 14 3.073630 3 + 15 3.159890 2 + 16 3.402650 5 + 17 3.507630 6 + 18 3.596340 3 + 19 3.674920 4 + 20 3.680680 3 + 21 3.723810 1 + 22 3.750900 2 + 23 3.753630 0 + 24 3.921960 5 + 25 3.962830 3 + 26 3.977910 0 - 27 4.191920 3 + 28 4.205860 4 + 29 4.349340 3 + 30 4.430720 2 - 31 4.480480 0 - 32 4.547920 2 + 33 4.599170 3 + 34 4.622380 2 - 35 4.705370 4 + 36 4.773350 4 + 37 4.939640 1 - 38 4.940790 5 + 39 4.952300 3 + 40 5.006660 2 - ----------------------- * Level density parameters (Gilbert-Cameron model/8/) Energy dependent parameters of Mengoni-Nakajima/9/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Al-27 4.651 2.309 -2.153 2.078 -0.772 17.788 5.960 Al-26 4.516 0.000 -2.370 1.927 -1.089 12.061 5.849 Al-25 4.381 2.400 -1.211 2.150 -1.367 17.328 5.526 Mg-26 4.790 4.707 -0.548 1.966 0.679 18.012 7.953 Mg-25 5.749 2.400 -1.351 1.415 1.633 9.704 6.362 Mg-24 4.244 4.899 -2.717 2.282 1.939 22.650 9.828 Na-25 4.381 2.400 0.883 1.731 0.184 10.755 5.876 Na-24 4.182 0.000 -0.676 2.101 -3.139 12.872 6.176 Na-23 4.106 2.502 -0.947 2.145 -0.474 15.832 8.476 Na-22 3.967 0.000 -1.620 2.198 -2.224 13.830 6.189 --------------------------------------------------------- * Gamma-ray strength functions for Al-27 E1: hybrid model(GH)/10/ ER= 22.29 (MeV) EG= 9.77 (MeV) SIG= 31.62 (mb) M1: standard lorentzian model(SLO) ER= 13.67 (MeV) EG= 4.00 (MeV) SIG= 3.45 (mb) E2: standard lorentzian model(SLO) ER= 21.00 (MeV) EG= 5.79 (MeV) SIG= 0.64 (mb) References 1) L.de Smet et al., Phys. Rev. C76, 045804 (2007) 2) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 3) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 4) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 5) Y.Han et al., Phys. Rev. C 74,044615(2006) 6) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 (2011) 7) M.Avrigeanu and V.Avrigeanu, Phys. Rev. C82, 014606 (2010) 8) A.Gilbert and A.G.W.Cameron, Can. J. Phys, 43, 1446 (1965) 9) A.Mengoni and Y.Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 10) S.Goriely, Phys. Lett. B436, 10 (1998)