6-C - 11 JAEA EVAL-Apr21 N.Iwamoto DIST-DEC21 20210401 ----JENDL-5 MATERIAL 622 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-04 Evaluated with CCONE code by N.Iwamoto 21-11 revised by O.Iwamoto (MF8/MT107) added MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Scattering radius only AP is assumed to be 4.4 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.45796E+02 Elastic 2.54671E+00 n,gamma 1.63503E-02 7.35589E-03 n,p 1.36653E+02 6.14791E+01 ---------------------------------------------------------- (*) 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= 28 (n,np) cross section Calculated with CCONE code /1/. MT= 44 (n,n2p) 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=106,750-799 (n,He3) cross section Calculated with CCONE code /1/. MT=107 (n,a) 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= 28 (n,np) reaction Calculated with CCONE code /1/. MT= 44 (n,n2p) 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=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=750-799 (n,He3) 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= 28 (n,np) reaction Decay chain is given in the decay data file. MT= 44 (n,n2p) 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=106 (n,He3) 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=107 (n,a) reaction Calculated with CCONE code /1/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al/2/ modified proton : global OMP, A.J.Koning and J.P.Delaroche/3/ deuteron: folding OMP, A.J.Koning and J.P.Delaroche/3/ triton : folding OMP, A.J.Koning and J.P.Delaroche/3/ He-3 : folding OMP, A.J.Koning and J.P.Delaroche/3/ alpha : V.Avrigeanu/4/ * Level scheme of C-11 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 3/2 - 1 2.000000 1/2 - 2 4.318800 5/2 - 3 4.804200 3/2 - 4 6.339200 1/2 + 5 6.478200 7/2 - 6 6.904800 5/2 + 7 7.400000 3/2 + 8 7.499700 3/2 + 9 8.104500 3/2 - 10 8.420000 5/2 - 11 8.654000 7/2 + 12 8.699000 5/2 + 13 9.200000 5/2 + 14 9.645000 3/2 - 15 9.780000 5/2 - 16 9.970000 7/2 - 17 10.083000 7/2 + ----------------------- * Level density parameters (Gilbert-Cameron model/5/) Energy dependent parameters of Mengoni-Nakajima/6/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- C-12 4.113 6.928 -5.786 2.398 6.852 30.342 11.828 C-11 2.287 3.618 -1.629 3.853 -1.554 28.948 10.083 C-10 2.171 7.589 1.103 3.880 0.414 28.194 6.580 B-11 2.240 3.618 -2.058 3.865 -0.611 28.948 12.040 B-10 2.475 0.000 -2.900 3.718 -4.669 27.630 8.070 B-9 2.606 4.000 -2.122 3.923 -5.317 36.149 2.780 Be-10 2.171 7.589 0.680 3.862 1.050 28.429 10.570 Be-9 2.336 4.000 -2.081 4.082 -3.489 34.441 6.760 Be-8 1.835 8.485 -4.748 4.629 6.670 41.282 20.200 --------------------------------------------------------- * Gamma-ray strength functions for C-12 E1: enhanced generalized lorentzian model(EGLO)/7/ ER= 22.79 (MeV) EG= 3.62 (MeV) SIG= 15.70 (mb) M1: standard lorentzian model(SLO) ER= 17.91 (MeV) EG= 4.00 (MeV) SIG= 0.79 (mb) E2: standard lorentzian model(SLO) ER= 27.52 (MeV) EG= 5.97 (MeV) SIG= 0.30 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 3) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 4) V.Avrigeanu, Phys. Rev. C82, 014606 (2010) 5) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) 6) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 7) J. Kopecky et al., Phys. Rev. C 47, 312 (1993)