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In this paper, the design of an innovative lead-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. In order to analyse the dynamic behaviour of the ELSY plant, a lumped-parameter model, based on mass and energy conservation equations, has been developed for the 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 the common requirements, such as those on steam pressure and temperature, additional physical constraints, like a lower limit of the feedwater temperature to avoid lead freezing in any operating condition. These issues have been taken into account while building the control structure. Different control strategies have also 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. Both the model and the control loops and feed-forward actions have been implemented in the MATLAB-Simulink environment. Model parameters have been derived from the ELSY European Project design data. The reliability of the proposed control system has been verified by the simulation of most common operational transients.
31 Dicembre 2010
Collaborazioni internazionali e sviluppo competenze in materia nucleare (P03 GOV)