Modeling and identification of a nuclear reactor with temperature effects and Xenon poisoning

Gábor, Attila; Fazekas, Csaba; Szederkényi, Gábor; Hangos, Katalin M.

doi:10.1109/iecon.2009.5414753

Cited by 8 publications

(2 citation statements)

References 17 publications

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“…Mathematical modelling has played an important role in the development of PWR. There have been various researchers such as [2], [3] and [4] who have produced mathematical models for PWR systems. However in 2010, Tahir et al [4] presented the concept of modelling using graph representation of a system based on chemical compound and its reactions as vertices and edges respectively.…”

Section: Introductionmentioning

confidence: 99%

Transformation of Pressurized Water Reactor (AP1000) to Fuzzy Graph

Ashaari

Ahmad²,

Mohamad

2018

MATEMATIKA

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Pressurized water reactor (PWR) type AP1000 is a third generation of a nuclear power plant. The primary system of PWR using uranium dioxide to generate heat energy via fission process. The process influences temperature, pressure and pH value of water chemistry of the PWR. The aim of this paper is to transform the primary system of PWR using fuzzy autocatalytic set (FACS). In this work, the background of primary system of PWR and the properties of the model are provided. The simulation result, namely dynamic concentration of PWR is verified against published data.

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Section: Introductionmentioning

confidence: 99%

Transformation of Pressurized Water Reactor (AP1000) to Fuzzy Graph

Ashaari

Ahmad²,

Mohamad

2018

MATEMATIKA

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“…Fazekas et al [21] modelled the primary loop of VVER-type nuclear reactor for control requirements. Gabor et al [22] discussed system identification of a LTI state-space model of a VVER-type nuclear reactor. Das et al [23] used system identification to develop plant model around different operating points during step-back transients.…”

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confidence: 99%

Dynamic modelling, simulation, and control design of a pressurized water-type nuclear power plant

Vajpayee

Becerra

Bausch

et al. 2020

Nuclear Engineering and Design

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This article presents an integrated non-linear dynamic model of a Pressurized Water-type Nuclear Reactor (PWR) and associated plant components for control design and evaluation purposes. The model uses the first-principles approach to represent various components of the plant. The model considers the dynamics of the reactor core, thermal hydraulics, piping and plenum, pressurizer, steam generator, condenser, and turbinegovernor system, in addition to various actuators and sensors. The response of the proposed model is tested using perturbations in different input variables. Various control loops implementing low-level PI control strategies are designed and implemented in the model to simulate the closed-loop behaviour of the plant. These include control loops for reactor power, steam generator pressure, pressurizer pressure and level, and turbine speed. Linear quadratic Gaussian-based optimal control strategies are further developed and implemented. Unique contributions of the work include the set of plant sections that are considered, the implementation of carefully tuned control strategies, the completeness of the model equations, and the availability of parameter values so that the model is readily implementable and has the potential to become a benchmark for control design studies in PWR nuclear power plants.

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