50-Sn-113 JAEA EVAL-Oct21 N.Iwamoto DIST-DEC21 20211029 ----JENDL-5 MATERIAL 5028 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-09 Evaluated with CCONE code by N.Iwamoto 21-11 JENDL-5rc1 revised by N.Iwamoto (MF2/MT151) revised MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Scattering radius only Resolved resonance region : below 340 eV Resolved resonance parameters were taken from Anufriev et al./1/. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.41441E+01 Elastic 5.13690E+00 n,gamma 9.00709E+00 2.32215E+02 n,p 2.84918E-07 4.61214E-06 n,alpha 1.12113E-04 2.02333E-03 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section 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= 17 (n,3n) cross section Calculated with CCONE code /2/. MT= 22 (n,na) cross section Calculated with CCONE code /2/. MT= 24 (n,2na) 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=111 (n,2p) cross section Calculated with CCONE code /2/. MT=112 (n,pa) 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= 17 (n,3n) reaction Calculated with CCONE code /2/. MT= 22 (n,na) reaction Calculated with CCONE code /2/. MT= 24 (n,2na) 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=111 (n,2p) reaction Calculated with CCONE code /2/. MT=112 (n,pa) 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= 17 (n,3n) 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= 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=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. MF= 9 Isomeric branching ratios MT=103 (n,p) reaction Calculated with CCONE code /2/. MF=10 Nuclide production reactions MT= 4 (n,n') 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=104 (n,d) reaction Calculated with CCONE code /2/. MT=105 (n,t) reaction Calculated with CCONE code /2/. MT=106 (n,He3) reaction Calculated with CCONE code /2/. MT=112 (n,pa) 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 Sn-113 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 1/2 + 1 0.077390 7/2 + 2 0.409830 5/2 + 3 0.498070 3/2 + 4 0.738400 11/2 - 5 1.013940 3/2 + 6 1.018080 5/2 + 7 1.042000 3/2 + 8 1.140000 1/2 + 9 1.248700 5/2 + 10 1.284060 5/2 + 11 1.303000 1/2 + 12 1.314070 3/2 + 13 1.355900 3/2 + 14 1.472540 5/2 + 15 1.537000 7/2 + 16 1.539000 5/2 + 17 1.539900 11/2 - 18 1.556500 3/2 + 19 1.646060 5/2 + 20 1.647200 7/2 + 21 1.651620 5/2 + 22 1.732220 5/2 + 23 1.744810 5/2 + 24 1.781100 9/2 - 25 1.821000 1/2 + 26 1.831000 1/2 + 27 1.867280 5/2 + 28 1.906600 15/2 - 29 1.909640 7/2 + 30 1.935400 11/2 - 31 1.945300 9/2 - 32 1.952100 13/2 - 33 1.957050 3/2 + 34 2.031400 5/2 - 35 2.039880 7/2 + 36 2.045470 5/2 + 37 2.050000 3/2 - 38 2.105000 3/2 - ----------------------- * 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 --------------------------------------------------------- Sn-114 14.672 2.248 0.682 0.628 0.960 6.199 3.297 Sn-113 14.860 1.129 0.757 0.615 -0.129 4.972 2.105 Sn-112 14.461 2.268 0.039 0.661 0.963 6.457 3.079 Sn-111 14.356 1.139 -0.025 0.711 -0.595 6.094 1.417 In-113 14.567 1.129 2.055 0.600 -0.291 4.968 1.980 In-112 14.461 0.000 1.669 0.561 -0.930 3.130 1.117 In-111 14.356 1.139 1.283 0.610 -0.082 4.846 2.142 In-110 14.250 0.000 0.827 0.599 -0.961 3.383 1.118 Cd-112 14.063 2.268 2.419 0.710 -0.302 7.759 3.205 Cd-111 14.785 1.139 2.384 0.663 -1.167 6.158 1.392 Cd-110 14.250 2.288 1.723 0.685 0.182 7.265 2.706 Cd-109 15.130 1.149 1.602 0.632 -0.677 5.605 1.318 Cd-108 14.038 2.309 0.685 0.741 0.068 7.845 3.171 --------------------------------------------------------- * Gamma-ray strength functions for Sn-114 E1: hybrid model(GH)/10/ ER= 15.79 (MeV) EG= 5.05 (MeV) SIG= 254.58 (mb) M1: standard lorentzian model(SLO) ER= 8.46 (MeV) EG= 4.00 (MeV) SIG= 0.96 (mb) E2: standard lorentzian model(SLO) ER= 12.99 (MeV) EG= 4.74 (MeV) SIG= 2.75 (mb) References 1) V.A.Anufriev et al., Atomnaya Energiya, 63, 397 (1987) 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)