Space-Time Nuclear Reactor Control for CANDUs, ACRs, ACR-BWRs, PWRs and BWRs

Abstract

A nonlinear modal control algorithm is described for CANDUs, ACRs, ACR-BWRs, PWRs and BWRs which can be implemented in advisory mode or direct mode on a PC. The modal control algorithm is composed of nonlinear feedforward and feedback control signals, a nonlinear reference model of the nuclear reactor, a nonlinear modal predictor, and a nonlinear feedforward control algorithm for refueling operations. Optimized control devices are described. 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. Control algorithms are described for variable coolant flow. The response of the modal control algorithm is described for AGC modes with daily and weekend load cycle operation. The modal control algorithm is stable and provides excellent response characteristics.