26-Fe- 55 JAEA EVAL-Jun21 N.Iwamoto DIST-DEC21 20210630 ----JENDL-5 MATERIAL 2628 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-06 Evaluated with CCONE code by N.Iwamoto MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Scattering radius only AP is assumed to be 5.48 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.76698E+02 Elastic 3.80913E+00 n,gamma 1.70061E+02 7.60111E+01 n,p 5.04811E-01 2.25837E-01 n,alpha 2.70096E-02 1.24027E-02 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /1/. MT= 2 Elastic scattering cross section Calculated with CCONE code /1/. MT=4,51-91 (n,n') cross section Calculated with CCONE code /1/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /1/. 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= 32 (n,nd) cross section Calculated with CCONE code /1/. MT= 41 (n,2np) 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/. 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=111 (n,2p) cross section Calculated with CCONE code /1/. MT=112 (n,pa) cross section Calculated with CCONE code /1/. MT=115 (n,pd) 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= 5 Total reaction (except fission) reaction Calculated with CCONE code /1/. 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= 32 (n,nd) reaction Calculated with CCONE code /1/. MT= 41 (n,2np) 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=111 (n,2p) reaction Calculated with CCONE code /1/. MT=112 (n,pa) reaction Calculated with CCONE code /1/. MT=115 (n,pd) 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= 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. MF=10 Nuclide production cross sections MT=108 (n,2a) reaction Calculated with CCONE code /1/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : A.J.Koning and J.P.Delaroche/2/ modified proton : global OMP, A.J.Koning and J.P.Delaroche/2/ deuteron: Y.Han et al./3/ triton : folding OMP, A.J.Koning and J.P.Delaroche/2/ He-3 : Y.Xu et al. /4/ alpha : L.McFadden and G.R.Satchler/5/ * Level scheme of Fe-55 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 3/2 - 1 0.411420 1/2 - 2 0.931290 5/2 - 3 1.316540 7/2 - 4 1.408450 7/2 - 5 1.918300 1/2 - 6 2.015000 3/2 - 7 2.051700 3/2 - 8 2.144000 5/2 - 9 2.211870 9/2 - 10 2.255500 9/2 - 11 2.301060 9/2 + 12 2.470200 3/2 - 13 2.490000 5/2 - 14 2.539110 11/2 - 15 2.577700 5/2 - 16 2.600000 9/2 + 17 2.813800 13/2 - 18 2.872300 7/2 - 19 2.938900 7/2 - 20 2.982100 11/2 - 21 2.984400 9/2 - 22 3.028500 3/2 - 23 3.072000 11/2 - 24 3.076000 11/2 - 25 3.108700 7/2 - 26 3.285000 1/2 + 27 3.311000 5/2 - 28 3.362000 11/2 + 29 3.419000 15/2 - 30 3.456900 13/2 - 31 3.552300 3/2 - 32 3.599000 1/2 - 33 3.660800 1/2 - 34 3.709000 9/2 - 35 3.722000 11/2 - 36 3.790300 1/2 - 37 3.800600 3/2 - 38 3.814000 3/2 - 39 3.815000 7/2 - 40 3.860000 5/2 - ----------------------- * Level density parameters (Gilbert-Cameron model/6/) Energy dependent parameters of Mengoni-Nakajima/7/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Fe-56 8.265 3.207 -2.152 1.503 -1.634 17.526 4.683 Fe-55 8.333 1.618 -2.981 1.428 -1.607 14.443 3.860 Fe-54 8.029 3.266 -3.371 1.524 -0.278 17.953 5.506 Mn-55 8.148 1.618 -1.124 1.431 -3.019 13.792 3.046 Mn-54 8.029 0.000 -2.202 1.328 -2.367 9.675 2.715 Mn-53 7.911 1.648 -2.189 1.410 -1.450 12.908 4.635 Cr-54 7.363 3.266 -0.310 1.482 -1.341 14.697 4.256 Cr-53 7.868 1.648 -1.137 1.298 -1.087 10.541 3.435 Cr-52 7.792 3.328 -1.323 1.378 0.001 13.627 4.100 Cr-51 7.669 1.680 -1.091 1.402 -1.932 12.211 4.707 Cr-50 6.722 3.394 -1.220 1.708 -1.871 17.835 5.336 --------------------------------------------------------- * Gamma-ray strength functions for Fe-56 E1: hybrid model(GH)/8/ ER= 17.33 (MeV) EG= 6.04 (MeV) SIG= 30.52 (mb) ER= 19.44 (MeV) EG= 7.52 (MeV) SIG= 61.03 (mb) M1: standard lorentzian model(SLO) ER= 10.72 (MeV) EG= 4.00 (MeV) SIG= 1.85 (mb) E2: standard lorentzian model(SLO) ER= 16.47 (MeV) EG= 5.44 (MeV) SIG= 1.32 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 3) Y.Han et al., Phys. Rev. C 74,044615(2006) 4) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 (2011) 5) L.McFadden and G.R.Satchler, Nucl. Phys. 84, 177 (1966) 6) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) 7) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 8) S. Goriely, Phys. Lett. B436, 10 (1998)