Application of On-Line Solution of3-Dirnensional Multi.group Finite-Difference Neutron Diffusion Equations in Reactor Power Control System

Abstract

The use of digital computers in on-line control of spatial power distribution, and power manoeuvres has been long established in CANDU reactors. The Power Mapping and Finite Difference (PMED) method cornbines the benefits of using fusion theory with actual measurements of neutron fluxes obtained kern self-powered flux detectors to calculate instantaneous channel power and bundle power distributions on-line, far use by the reactor regulating system. The PMFD approach is more accurate than the presently used flux synthesis approach and it is also less sensitive to random and systematic detector errors.