A method of channel-by-channel calculation of a nuclear reactor based on coarse grid

An approach to developing the coarse-mesh model of a nuclear reactor is described. The model is based on two-stage scheme of power density distribution calculation including the one-group coarse-mesh diffusion calculation of neutron flux averaged by cells, which conditionally form the reactor core, the reconstruction of by-channel power density distribution inside a macrocell on the base of the values of neutron flux in adjacent macrocells obtained at the first stage. The model of this type can be used as a part of special software for the system of centralized control, as well as the basis model for imitator of nuclear reactor neutron-physical characteristics for NPP simulator besides studying into stationary and transient processes. 11 refs., 1 tab., 2 figs