In this paper a fuzzy logic controller is applied to control the steam generator water level in a pressurized water reactor. The method does not require a detailed mathematical mode of the object to be controlled. The design is based on a set of linguistic rules that were adopted from the human operator's experience. After off-line fuzzy computation, the controller is a lookup table, and thus, real-time control is achieved. Shrink-and-swell phenomena are considered in the linguistic rules, and the simulation results show that their effect is dramatically reduced. The performance of the control system can also be improved by changing the input and output scaling factors, which is convenient for on-line tuning.

Fuzzy Logic Control of Steam Generator Water Level in Pressurized Water Reactors

A fuzzy-gain-scheduled neural controller for nuclear steam generators

Gain scheduled dynamic sliding mode control for nuclear steam generators

Control of the nuclear steam generators using adaptive dynamic sliding mode method based on the nonlinear model

Adaptive estimator-based dynamic sliding mode control for the water level of nuclear steam generators

The authors consider the design of a suboptimal water-level controller for steam generators in large pressurized water reactors using linear output feedback control. A methodology for feasibility analysis and linear output feedback control design is developed through eigenvalue dynamics. The proposed controller is a linear, constant, partial state feedback law. The controlled system has the following desirable features: (a) the controller is independent of disturbance, (b) the water level returns to its prespecified level value following a step disturbance, (c) the controlled system is asymptotically stable, and (d) transient response is similar to the transient response of an optimal complete state feedback controller. An example illustrates the applicability and the effectiveness of the proposed techniques. >

Lotfi A. Belblidia

Papers

Optimal Level Controller for Steam Generators in Pressurized Water Reactors