38-Sr- 87 JAEA EVAL-Apr21 N.Iwamoto DIST-DEC21 20210401 ----JENDL-5 MATERIAL 3834 -----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 14.08 keV Evaluation of JENDL-2 was performed on the basis of the measurements by Camarda et al./1/ and Musgrove et al./2/ Neutron widths were derived from the data of 2g*(neutron width) and neutron capture areas. Neutron orbital angular momentum L was assumed to be 0 for all resonance levels except the 2nd level (L=1) at 35.27 eV. However, the values of total spin J were unknown for all resonance levels. Thus, target spin of 4.5 was adopted as J value. Average radiation width of 180.4 meV was obtained by averaging the given radiation widths. hHwever, this value was reduced to 110.72 meV so as to reproduce the neutron capture resonance integral of 118+-30 barns given by Mughabghab et al./3/ A negative resonance was also added at -50 eV, and the parameters were adjusted so as to reproduce the thermal capture cross section of 16(3) barns given by Mughabghab et al. For JENDL-3, the values of total spin J were tentatively estimated with a random number method. Neutron widths were modified on the basis of the estimated J-values. Radiation width of the negative level was slightly adjusted so as to reproduce the thermal capture cross section according to the modification of the positive levels. Scattering radius was taken from the graph (fig. 1, Part A) given by Mughabghab et al. In JENDL-4, the radiation width of the negative resonance was changed to 145 meV. Unresolved resonance region: 14.08 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 2.39750E+01 Elastic 6.93822E+00 n,gamma 1.70367E+01 1.21329E+02 n,p 5.56930E-13 2.12540E-13 n,alpha 3.11840E-16 8.16814E-15 ---------------------------------------------------------- (*) 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= 32 (n,nd) 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= 32 (n,nd) 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= 32 (n,nd) 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=10 Nuclide production cross sections MT=4 (n,n') 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=104 (n,d) reaction Calculated with CCONE code /5/. MT=106 (n,He3) reaction Calculated with CCONE code /5/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /5/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al/6/ modified proton : global OMP, A.J.Koning and J.P.Delaroche/7/ 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-87 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 9/2 + 1 0.388530 1/2 - 2 0.873340 3/2 - 3 1.228420 5/2 + 4 1.253940 5/2 - 5 1.740000 13/2 + 6 1.742000 5/2 + 7 1.770460 5/2 + 8 1.920480 7/2 + 9 2.110050 3/2 - 10 2.153500 11/2 + 11 2.169420 1/2 + 12 2.235700 9/2 + 13 2.262000 7/2 + 14 2.414500 3/2 - 15 2.420400 5/2 - 16 2.488000 7/2 + 17 2.532800 9/2 + 18 2.536300 11/2 - 19 2.539000 11/2 + 20 2.550000 7/2 + 21 2.555000 9/2 - 22 2.596000 13/2 - 23 2.631000 1/2 - 24 2.656000 7/2 - 25 2.676840 3/2 + 26 2.679000 1/2 - 27 2.682000 3/2 + 28 2.707500 7/2 + 29 2.803150 7/2 + 30 2.818890 9/2 + 31 2.821000 9/2 + 32 2.831200 15/2 - 33 2.850520 1/2 - 34 2.893000 7/2 + 35 2.904100 5/2 + 36 2.920800 7/2 + 37 2.921090 3/2 - 38 2.940690 1/2 + 39 2.980000 1/2 + 40 3.007170 3/2 - ----------------------- * 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-88 10.482 2.558 -1.514 0.940 1.282 8.258 4.846 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 Rb-87 11.777 1.287 -0.782 0.782 0.223 5.670 2.555 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 Kr-86 11.667 2.588 -0.512 0.711 1.970 5.975 4.194 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 --------------------------------------------------------- * Gamma-ray strength functions for Sr-88 E1: hybrid model(GH)/13/ ER= 16.78 (MeV) EG= 5.68 (MeV) SIG= 174.28 (mb) M1: standard lorentzian model(SLO) ER= 9.22 (MeV) EG= 4.00 (MeV) SIG= 1.18 (mb) E2: standard lorentzian model(SLO) ER= 14.16 (MeV) EG= 5.05 (MeV) SIG= 1.93 (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)