Operational Analysis of Multiregional Nuclear Reactor Kinetics

A general procedure for solving the boundary-value problem ofthe unsteady multigroup coupled neutron diffusion and precursorequations is developed analytically for a multiregional nuclearreactor whose subregions are of arbitrary shapes and with arbitraryspace-time dependent neutron multiplication properties. Themethod which is based on the formulation and application ofcomposite region integral transforms is seen to accept variousorders of analytical approximations that originate from thetransformed space. The formalism does not cover circulatingfuel precursors.