38-Sr- 86 JAEA EVAL-Apr21 N.Iwamoto DIST-DEC21 20210401 ----JENDL-5 MATERIAL 3831 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-04 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 Resolved and unresolved resonance parameters Resolved resonance region (MLBW formula) : below 37.12 keV The resolved resonance parameters for JENDL-3 were taken from JENDL-2 which was evaluated on the basis of the measured data by Camarda et al./1/ and Musgrove et al./2/ Those of the first resonance level at 588.4 eV were adjusted so as to reproduce the capture cross section of 1.04+-0.07 barns at 0.0253 eV and its resonance integral of 4.79+-0.24 barns given by Mughabghab et al./3/ Scattering radius was also modified to 7.25 fm on the basis of the graph (Fig.1, part A) of Ref./3/ In JENDL-5, the resolved resonance parameters remain unchanged. Unresolved resonance region: 37.12 keV - 1 MeV The unresolved resonance paramters (URP) were determined by ASREP code /4/ so as to reproduce the evaluated total and capture cross sections. The unresolved parameters should be used only for self-shielding calculation. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 5.19820E+00 Elastic 4.15782E+00 n,gamma 1.04038E+00 4.70126E+00 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /5/. MT= 2 Elastic scattering cross section Calculated with CCONE code /5/. MT=4,51-91 (n,n') cross section Calculated with CCONE code /5/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /5/. MT= 16 (n,2n) cross section Calculated with CCONE code /5/. MT= 22 (n,na) cross section Calculated with CCONE code /5/. MT= 28 (n,np) cross section Calculated with CCONE code /5/. MT=102 Capture cross section Calculated with CCONE code /5/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /5/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /5/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /5/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /5/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /5/. MT=111 (n,2p) cross section Calculated with CCONE code /5/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /5/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /5/. MT= 16 (n,2n) reaction Calculated with CCONE code /5/. MT= 22 (n,na) reaction Calculated with CCONE code /5/. MT= 28 (n,np) reaction Calculated with CCONE code /5/. MT=51-91 (n,n') reaction Calculated with CCONE code /5/. MT=102 Capture reaction Calculated with CCONE code /5/. MT=111 (n,2p) reaction Calculated with CCONE code /5/. MT=600-649 (n,p) reaction Calculated with CCONE code /5/. MT=650-699 (n,d) reaction Calculated with CCONE code /5/. MT=700-749 (n,t) reaction Calculated with CCONE code /5/. MT=750-799 (n,He3) reaction Calculated with CCONE code /5/. MT=800-849 (n,a) reaction Calculated with CCONE code /5/. 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=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. MF= 9 Isomeric branching ratios MT=102 Capture reaction Calculated with CCONE code /5/. MT=107 (n,a) reaction Calculated with CCONE code /5/. MF=10 Nuclide production cross sections MT= 16 (n,2n) reaction Calculated with CCONE code /5/. MT=103 (n,p) reaction Calculated with CCONE code /5/. MT=105 (n,t) reaction Calculated with CCONE code /5/. MT=111 (n,2p) reaction Calculated with CCONE code /5/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /5/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al/6/ modified proton : A.J.Koning and J.P.Delaroche/7/ modified deuteron: Y.Han et al./8/ triton : folding OMP, A.J.Koning and J.P.Delaroche/7/ He-3 : Y.Xu et al./9/ alpha : V.Avrigeanu/10/ * Level scheme of Sr-86 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 1.076680 2 + 2 1.854170 2 + 3 2.106000 0 + 4 2.203000 0 + 5 2.229740 4 + 6 2.365000 1 - 7 2.481910 3 - 8 2.497000 4 - 9 2.642190 2 + 10 2.672840 5 - 11 2.788500 2 + 12 2.857000 6 + 13 2.878280 4 + 14 2.955680 8 + 15 2.997360 3 - 16 3.045000 3 - 17 3.055780 5 - 18 3.104000 0 + 19 3.185000 5 - 20 3.185230 3 - 21 3.291300 3 - 22 3.317620 5 - 23 3.362070 4 + 24 3.392000 5 - 25 3.430000 2 + 26 3.482200 6 + 27 3.499910 4 - 28 3.500500 5 - 29 3.555780 4 + ----------------------- * Level density parameters (Gilbert-Cameron model/11/) Energy dependent parameters of Mengoni-Nakajima/12/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Sr-87 10.428 1.287 -0.027 0.925 -0.609 7.203 3.007 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 Rb-86 10.093 0.000 0.004 0.930 -1.736 5.718 1.558 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 Kr-85 10.901 1.302 0.713 0.809 -0.204 6.032 2.637 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 --------------------------------------------------------- * Gamma-ray strength functions for Sr-87 E1: hybrid model(GH)/13/ ER= 16.82 (MeV) EG= 5.71 (MeV) SIG= 171.87 (mb) M1: standard lorentzian model(SLO) ER= 9.25 (MeV) EG= 4.00 (MeV) SIG= 1.19 (mb) E2: standard lorentzian model(SLO) ER= 14.22 (MeV) EG= 5.07 (MeV) SIG= 1.95 (mb) References 1) H.Camarda et al., NCSAC-31, 40 (1970). 2) A.R.de L.Musgrove et al., Proc. Int. Conf. on Neutron Physics and Nucl. Data for Reactors, Harwell 1978, 449. 3) S.F.Mughabghab, "Atlas of Neutron Resonances", Elsevier (2006). 4) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999) [in Japanese] 5) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 6) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 7) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 8) Y.Han et al., Phys. Rev. C 74,044615(2006) 9) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 10) V.Avrigeanu, Phys. Rev. C82, 014606 (2010) 11) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) 12) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 13) S. Goriely, Phys. Lett. B436, 10 (1998)