38-Sr- 85 JAEA EVAL-Mar21 N.Iwamoto DIST-DEC21 20210331 ----JENDL-5 MATERIAL 3828 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-03 Evaluated with CCONE code by N.Iwamoto 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Scattering radius only No resolved resonance parameters Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.58603E+01 Elastic 6.37315E+00 n,gamma 9.20598E+00 1.94407E+02 n,p 1.04207E-03 2.30015E-02 n,alpha 4.00164E-08 1.35457E-06 ---------------------------------------------------------- (*) 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=111 (n,2p) cross section Calculated with CCONE code /1/. MT=112 (n,pa) 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=111 (n,2p) reaction Calculated with CCONE code /1/. MT=112 (n,pa) 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=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=10 Nuclide production cross sections MT=4 (n,n') 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=104 (n,d) reaction Calculated with CCONE code /1/. MT=106 (n,He3) 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: Y.Han et al./4/ triton : folding OMP, A.J.Koning and J.P.Delaroche/3/ He-3 : Y.Xu et al./5/ alpha : V.Avrigeanu/6/ * Level scheme of Sr-85 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 9/2 + 1 0.231670 7/2 + 2 0.238660 1/2 - 3 0.743130 3/2 - 4 0.767270 5/2 + 5 0.785440 5/2 - 6 0.936750 5/2 - 7 1.111300 13/2 + 8 1.152600 3/2 - 9 1.220720 11/2 + 10 1.261920 9/2 + 11 1.355060 5/2 + 12 1.403000 1/2 + 13 1.404900 3/2 + 14 1.405110 5/2 - 15 1.453000 9/2 - 16 1.485600 3/2 + 17 1.516800 1/2 + 18 1.555280 5/2 + 19 1.559300 3/2 + 20 1.588480 9/2 + 21 1.627050 9/2 + 22 1.648700 1/2 - 23 1.657700 11/2 + 24 1.684200 11/2 + 25 1.700950 9/2 - 26 1.712000 1/2 + 27 1.793000 5/2 + 28 1.793600 7/2 - 29 1.827000 5/2 + 30 1.842000 1/2 + ----------------------- * Level density parameters (Gilbert-Cameron model/7/) Energy dependent parameters of Mengoni-Nakajima/8/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Sr-86 11.667 2.588 0.762 0.781 0.918 7.404 3.556 Sr-85 11.329 1.302 1.859 0.838 -1.237 7.096 1.842 Sr-84 11.447 2.619 1.982 0.727 1.057 6.879 3.332 Rb-85 11.557 1.302 1.525 0.811 -0.940 6.735 1.496 Rb-84 11.447 0.000 2.111 0.785 -2.174 5.139 0.718 Rb-83 11.337 1.317 2.990 0.822 -1.573 7.172 1.243 Kr-84 9.655 2.619 1.222 0.995 -0.055 9.331 3.476 Kr-83 11.337 1.317 2.368 0.768 -0.737 6.210 1.781 Kr-82 11.226 2.650 2.496 0.764 0.641 7.448 3.187 Kr-81 11.187 1.333 3.298 0.819 -1.588 7.129 1.351 Kr-80 11.004 2.683 3.044 0.683 1.318 6.404 3.173 --------------------------------------------------------- * Gamma-ray strength functions for Sr-86 E1: hybrid model(GH)/9/ ER= 16.87 (MeV) EG= 5.74 (MeV) SIG= 169.44 (mb) M1: standard lorentzian model(SLO) ER= 9.29 (MeV) EG= 4.00 (MeV) SIG= 1.21 (mb) E2: standard lorentzian model(SLO) ER= 14.27 (MeV) EG= 5.08 (MeV) SIG= 1.97 (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) Y.Han et al., Phys. Rev. C 74,044615(2006) 5) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 6) V.Avrigeanu, Phys. Rev. C82, 014606 (2010) 7) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) 8) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 9) S. Goriely, Phys. Lett. B436, 10 (1998)