Method for calculation of the stability of a boiling water channel reactor

A model of neutron transport in a nuclear reactor core is considered in general terms. The model constitUtes a time-dependent one-group diffusion equation with arbitrary boundary conditions. Heat transfer in fuel elements is described by the time-dependent heat-conductivity equation. On the basis of these models and the time-dependent equation describing one-dimensional two-phase flow of a coolant, a closed nonlinear set of equations for the dynamics of a boiling channel-type reactor has been obtained. By linearizing this set in the vicinity of a stationary solution, sufficient conditions of stability (in small) of the reactor steady-state mode have been derived