Model predictive control of the hybrid primary circuit dynamics in a pressurized water nuclear power plant

Author(s):  
Tamas Peni ◽  
Gabor Szederkenyi ◽  
Jozsef Bokor
2014 ◽  
Vol 2014 ◽  
pp. 1-10 ◽  
Author(s):  
Xiangjie Liu ◽  
Mengyue Wang

Reliable power and temperature control in pressurized water reactor (PWR) nuclear power plant is necessary to guarantee high efficiency and plant safety. Since the nuclear plants are quite nonlinear, the paper presents nonlinear fuzzy model predictive control (MPC), by incorporating the realistic constraints, to realize the plant optimization. T-S fuzzy modeling on nuclear power plant is utilized to approximate the nonlinear plant, based on which the nonlinear MPC controller is devised via parallel distributed compensation (PDC) scheme in order to solve the nonlinear constraint optimization problem. Improved performance compared to the traditional PID controller for a TMI-type PWR is obtained in the simulation.


2008 ◽  
Vol 41 (2) ◽  
pp. 10640-10645
Author(s):  
Csaba Fazekas ◽  
Gábor Szederkényi ◽  
Katalin M. Hangos

2013 ◽  
Vol 23 (4) ◽  
pp. 455-471 ◽  
Author(s):  
Mariusz Czapliński ◽  
Paweł Sokólski ◽  
Kazimierz Duzinkiewicz ◽  
Robert Piotrowski ◽  
Tomasz Rutkowski

Abstract The pressurizer water level control system in nuclear power plant with pressurized water reactor (PWR) is responsible for coolant mass balance. The main control goal is to stabilize the water level at a reference value and to suppress the effect of time-varying disturbances (e.g. coolant leakage in primary circuit pipeline system). In the process of PWR power plant operation incorrect water level may disturb pressure control or may cause damage to electric heaters which could threaten plant security and stability. In modern reactors standard PID controllers are used to control water level in a pressurizer. This paper describes the performance of state feedback integral controller (SFIC) with reduced-order Luenberger state observer designed for water level control in a pressurizer and compares it to the standard PID controller. All steps from modeling of a pressurizer through control design to implementation and simulation testing in Matlab/Simulink environment are detailed in the paper.


Author(s):  
Xiao Yuan ◽  
Minjun Peng ◽  
Genglei Xia

The passive safety systems employed in the design of pressurized water reactor (PWR) can accomplish the inherent safety functions and mitigate the consequences of the postulated accidents. In this paper, a passive residual heat removal system (PRHRs) is designed for a certain nuclear power plant. The RELAP5/MOD3.4 code was used to analyze the operation characteristics of the PRHRs. It shows the PRHRs could remove the decay heat from the primary loop effectively, and the single-phase and two-phase natural circulations could respectively establish in the primary circuit and the PRHRs circuit.


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