Abstract
AbstractIn this paper, the design of an innovative liquid metal-cooled fast nuclear reactor is considered, with specific reference to the European Lead-cooled SYstem (ELSY) project, complying with the Generation IV International Forum (GIF) requirements. A lumped-parameter dynamic model, based on mass and energy conservation equations, has been developed for the ELSY plant secondary system. This includes, in particular, the lead-water steam generators, which have a main role in the feedback between the primary and secondary system and whose operation has to satisfy, beside common requirements on steam pressure and temperature, additional physical constraints, like a lower limit of the feedwater temperature to avoid lead freezing in any operating condition.Different control strategies have been set up for different operating conditions, such as the normal mode and the alternate mode; these are characterised by different plant subsystem configurations and can be compared to the well-known coordinated mode and turbine-following mode for conventional thermal power plants, respectively.The model and the control loops and feedforward actions have been implemented in the MATLAB-Simulink® environment, with model parameters derived from design data. The control system reliability has been verified by simulating most common operational transients.
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