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- W2045202391 abstract "This paper presents the development of a three-dimensional space-time neutronic kinetic model of a Canadian deuterium uranium (CANDU) reactor using a modal method. In this method, the reactor space-time neutron flux is synthesized by a time-weighted series of precalculated 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 a CANDU6 reactor regulating system in MATLAB/SIMULINK. A nondimensionalized SIMULINK representation of the reactor kinetic model is established. The behavior of the reactor during load following transients has been simulated using the developed reactor-modeling module. The simulation results prove the efficiency of the model. A three-dimensional neutron flux distribution during transients is represented." @default.
- W2045202391 created "2016-06-24" @default.
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- W2045202391 date "2010-12-21" @default.
- W2045202391 modified "2023-09-27" @default.
- W2045202391 title "CANDU Reactor Space-Time Kinetic Model for Load Following Studies" @default.
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- W2045202391 doi "https://doi.org/10.1115/1.4002870" @default.
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