CANDU REACTOR SPACE-TIME KINETIC MODELING FOR LOAD FOLLOWING CONTROL
This paper presents the development of a three-dimensional space-time neutronic kinetic modeling of a CANadian Deuterium Uranium (CANDU) reactor for control system design and research, using a modal method. In this method, the reactor space-time neutron flux is synthesized by a time-weighted series of pre-calculated neutron flux modes. The modes are eigenfunctions of the governing neutron diffusion equation during reference steady-state operation. The Xenon effect has also been considered. The reactor model is then implemented within a simulation platform of CANDU6 reactor regulating system (RRS), in MATLAB/SIMULINK. Non-dimensionalized SIMULINK representation of the reactor kinetic modeling is established. Behavior of the reactor during a load following transient has been simulated using the developed reactor-modeling module. The simulation results prove the efficiency of the reactor modeling. Real-time three-dimensional neutron flux distribution during the transient analysis is represented.
Lingzhi Xia Jin Jiang
Department of Electrical and Computer Engineering University of Western Ontario London, Ontario, N6A Department of Electrical and Computer Engineering University of Western Ontario London, Ontario, N6A
国际会议
18th International Conference on Nuclear Engineering(第18届国际核能工程大会 ICONE 18)
西安
英文
1-10
2010-05-17（万方平台首次上网日期，不代表论文的发表时间）