38-Sr- 84 JAEA EVAL-Apr21 N.Iwamoto DIST-DEC21 20210401 ----JENDL-5 MATERIAL 3825 -----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 4 keV The resonance parameters were taken from the work of Mughabghab /1/. The energy of a negative resonance was changed to -0.370 keV. Unresolved resonance region: 3.4 keV - 1 MeV The unresolved resonance paramters (URP) were determined by ASREP code /2/ 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 6.40260E+00 Elastic 5.57487E+00 n,gamma 8.27727E-01 1.11271E+01 n,alpha 2.80130E-16 2.76529E-15 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /3/. MT= 2 Elastic scattering cross section Calculated with CCONE code /3/. MT=4,51-91 (n,n') cross section Calculated with CCONE code /3/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /3/. MT= 16 (n,2n) cross section Calculated with CCONE code /3/. MT= 22 (n,na) cross section Calculated with CCONE code /3/. MT= 28 (n,np) cross section Calculated with CCONE code /3/. MT= 44 (n,n2p) cross section Calculated with CCONE code /3/. MT=102 Capture cross section Calculated with CCONE code /3/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /3/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /3/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /3/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /3/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /3/. MT=111 (n,2p) cross section Calculated with CCONE code /3/. MT=112 (n,pa) cross section Calculated with CCONE code /3/. MT=115 (n,pd) cross section Calculated with CCONE code /3/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /3/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /3/. MT= 16 (n,2n) reaction Calculated with CCONE code /3/. MT= 22 (n,na) reaction Calculated with CCONE code /3/. MT= 28 (n,np) reaction Calculated with CCONE code /3/. MT= 44 (n,n2p) reaction Calculated with CCONE code /3/. MT=51-91 (n,n') reaction Calculated with CCONE code /3/. MT=102 Capture reaction Calculated with CCONE code /3/. MT=111 (n,2p) reaction Calculated with CCONE code /3/. MT=112 (n,pa) reaction Calculated with CCONE code /3/. MT=115 (n,pd) reaction Calculated with CCONE code /3/. MT=600-649 (n,p) reaction Calculated with CCONE code /3/. MT=650-699 (n,d) reaction Calculated with CCONE code /3/. MT=700-749 (n,t) reaction Calculated with CCONE code /3/. MT=750-799 (n,He3) reaction Calculated with CCONE code /3/. MT=800-849 (n,a) reaction Calculated with CCONE code /3/. 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= 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=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. MT=115 (n,pd) reaction Decay chain is given in the decay data file. MF= 9 Isomeric branching ratios MT=102 Capture reaction Calculated with CCONE code /3/. MT=107 (n,a) reaction Calculated with CCONE code /3/. MF=10 Nuclide production cross sections MT= 16 (n,2n) reaction Calculated with CCONE code /3/. MT=103 (n,p) reaction Calculated with CCONE code /3/. MT=105 (n,t) reaction Calculated with CCONE code /3/. MT=111 (n,2p) reaction Calculated with CCONE code /3/. MT=112 (n,pa) reaction Calculated with CCONE code /3/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /3/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al/4/ modified proton : A.J.Koning and J.P.Delaroche/5/ modified deuteron: Y.Han et al./6/ triton : folding OMP, A.J.Koning and J.P.Delaroche/5/ He-3 : Y.Xu et al./7/ alpha : V.Avrigeanu/8/ * Level scheme of Sr-84 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 0.793220 2 + 2 1.453930 2 + 3 1.504200 0 + 4 1.767690 4 + 5 2.056070 3 + 6 2.071600 0 + 7 2.297930 2 - 8 2.390000 2 - 9 2.448110 3 - 10 2.525000 0 + 11 2.598230 4 + 12 2.735250 5 + 13 2.769030 5 - 14 2.807870 6 + 15 2.886990 2 + 16 3.041250 5 - 17 3.098670 6 + 18 3.157050 7 + 19 3.175000 2 + 20 3.255000 3 - 21 3.270580 4 + 22 3.279150 6 - 23 3.330000 0 + 24 3.331910 8 + ----------------------- * Level density parameters (Gilbert-Cameron model/9/) Energy dependent parameters of Mengoni-Nakajima/10/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- 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 Sr-83 11.337 1.317 2.694 0.889 -2.249 8.157 0.963 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 Rb-82 11.226 0.000 3.246 0.821 -2.927 5.828 0.340 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 Kr-79 10.893 1.350 3.558 0.823 -1.551 7.064 1.550 --------------------------------------------------------- * Gamma-ray strength functions for Sr-85 E1: hybrid model(GH)/11/ ER= 16.92 (MeV) EG= 5.77 (MeV) SIG= 166.97 (mb) M1: standard lorentzian model(SLO) ER= 9.32 (MeV) EG= 4.00 (MeV) SIG= 1.22 (mb) E2: standard lorentzian model(SLO) ER= 14.33 (MeV) EG= 5.09 (MeV) SIG= 1.99 (mb) References 1) S.F.Mughabghab, "Atlas of Neutron Resonances", Elsevier (2006). 2) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999) [in Japanese] 3) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 4) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 5) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 6) Y.Han et al., Phys. Rev. C 74,044615(2006) 7) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 8) V.Avrigeanu, Phys. Rev. C82, 014606 (2010) 9) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) 10) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 11) S. Goriely, Phys. Lett. B436, 10 (1998)