Derive two-group diffusion equations for a critical homogeneous reactor in steady state.
For a homogeneous reactor in steady state, we consider a two-group neutron diffusion model with fast ((1)) and thermal ((2)) neutrons. Let ( \phi_1 ) and ( \phi_2 ) be the neutron fluxes for the fast and thermal groups, ( D_1, D_2 ) the diffusion coefficients, ( \Sigma_{a1}, \Sigma_{a2} ) the absorption cross-sections, and ( \Sigma_{s12} ) the scattering cross-section ____ _________ ______ ______ ______ ___.
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