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• W2167470202 abstract "A simple dynamic model in physical coordinates and the corresponding parameter estimation procedure for the primary circuit dynamics and premodeling studies of the secondary circuit of VVER-type pressurized water reactors are presented in this paper. The primary uses of the model are control oriented dynamic model analysis and high level controller design. Therefore, the model should contain the minimal possible number of differential equations and it should be capable of describing important dynamic phenomena such as load change transients between day and night periods. Further- more, the estimated parameter values should fall into physically meaningful ranges. The parameter estimation method of the primary circuit is an optimization based numerical method using the decomposed and the entire primary circuit model. The partial verification of the models of parts of the secondary cir- cuit has also been completed using badly sampled measurments. The constructed model satisfies the predefined requirements and its response shows good fit to the measurement data that were obtained from three units of the Paks Nuclear Power Plant in Hungary. I. INTRODUCTION The physical and moral lifetime of instruments and con- trols installed in electricity generating plants is generally shorter than the expected service time of the power gen- erating unit itself. This fact often necessitates the re-tuning or the review of different subsystems in nuclear power plants (NPP). This requirement of re-tuning or review is strength- ened by the gradually changing operating requirements, the ever stringent regulations related to performance, effective- ness and safety. These important tasks are supported by the improving quantity and quality of dynamic measurements as a result of developing hardware-software environment and modern sensor devices. It is well known from theory and engineering practice that the application of advanced feedback control can dramatically improve dynamical system properties often without the need to introduce significant changes in the technology. Majority of the model analysis and controller design methods require that the original mathematical model of the system is in the form of (a preferably low number of) ordinary differential equations while the traditionally available and commonly used dynamic models for nuclear power plants (e.g. (6), (10)) are much too complex and detailed for control purposes. Relatively few publications can be found in the literature about the dynamic identification of simplified physical NPP models (2)." @default.
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• W2167470202 title "Modeling and Parameter Estimation of a Nuclear Power Plant" @default.
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