Advanced Nuclear Reactor Control Technology for Scalable Multi-Fuel Optimized Canadian Reactors (OCRs)

Abstract

An advanced modal control algorithm for variable load operation is described for scalable multi-fuel Optimized CANDU Reactors (OCRs). New optimized control devices are described. OCR sizes of 300, 1200, 2830 MWe are described. The modal control algorithm is composed of nonlinear feedforward and feedback control signals. The feedforward control algorithms are based on a modal model of the nuclear reactor with single-phase thermal-hydraulics. A modal analyzer is described which determines the modal amplitudes for neutron density from the array of detectors in the reactor. A bundle modal synthesizer is described which determines the bundle values for the nuclear and thermal-hydraulic variables from the neutron density modal amplitudes. Modal synthesizer displays for operator decision support are described. The response of the advanced nuclear reactor control algorithm is described for variable load operation scenarios using four different fuels. The advanced nuclear reactor control algorithms run on a PC and can be integrated into DCSs. A high speed data acquisition system is used to acquire and process detector and thermal-hydraulics data. The advanced nuclear reactor control system can operate in direct or advisory mode. Keywords: Space-Time Nuclear Reactor Control, Variable-Load, Modal Analysis and Synthesis.