共查询到20条相似文献,搜索用时 31 毫秒
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Poor control of U-tube steam generators (UTSG) in a nuclear power plant can lead to frequent reactor shutdowns or damage of turbine blades. The dynamics of steam generator vary as power level changes. There is, therefore, a need to systematically design a suitable controller for all power levels. In this paper, we employ the concepts of both predictive control and fuzzy set theory to design an appropriate control for UTSG water level. The controller has three main parts: (1) a TSK fuzzy model used for predicting the future behavior of UTSG, (2) a recursive algorithm to estimate parameters of this model and (3) a model predictive controller used to obtain optimal input control sequence. Simulation results show that the proposed controller has a remarkable performance for tracking the step and ramp reference trajectories while at the same time it is robust against steam flowrate changes. 相似文献
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为克服传统的核动力蒸汽发生器水位PID控制器存在的缺点,利用模糊推理技术和数字信号处理器(DSP)技术设计了基于DSP的核动力蒸汽发生器水位模糊控制系统。通过总结熟练操作人员的经验,给出了模糊控制规则,确定了一些重要的控制参数。考虑到控制的实时性,系统的稳定性,采用DSP设计了水位模糊控制系统。仿真实验表明,该系统性能良好。 相似文献
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A fuzzy controller design for nuclear research reactors using the particle swarm optimization algorithm 总被引:1,自引:0,他引:1
Ramazan Coban Author Vitae 《Nuclear Engineering and Design》2011,241(5):1899-1908
In this paper, a closed-loop fuzzy logic controller based on the particle swarm optimization algorithm is proposed for controlling the power level of nuclear research reactors. The principle of the fuzzy logic controller is based on the rules constructed from numerical experiments made by means of a computer code for the core dynamics calculation and from human operator's experience and knowledge. In addition to these intuitive and experimental design efforts, consequent parts of the fuzzy rules are optimally (or near optimally) determined using the particle swarm optimization algorithm. The contribution of the proposed algorithm to a reactor control system is investigated in details. The performance of the controller is also tested with numerical simulations in numerous operating conditions from various initial power levels to desired power levels, as well as under disturbance. It is shown that the proposed control system performs satisfactorily under almost all operating conditions, even in the case of very small initial power levels. 相似文献
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U-Tube Steam Generator (UTSG) is one of the most important facilities in a pressurized-water nuclear reactor. Poor control of the Steam Generator (SG) water level in the secondary circuit of a nuclear power plant can lead to frequent reactor shutdowns or damage of turbine blades. The control problem is challenging, especially at low power levels due to shrink and swell phenomena and flow measurement errors. In addition, the dynamics of steam generator vary as the power level changes. Therefore, designing a suitable controller for all power levels is a necessary step to enhance the plant availability factor. The purpose of this paper is to design, analyze and evaluate a water level controller for U-tube steam generators using dynamic sliding mode control. The employed method is easy to implement in practical applications and moreover, the dynamic sliding mode control exhibits the desired dynamic properties during the entire output-tracking process independent of perturbations. Gain scheduling is used to obtain a global water level controller. Simulation results are presented to demonstrate the performance, robustness, and stability of the proposed controller.Computer simulations show that the proposed controller improves the transient response of steam generator water level and demonstrates its superiority to existing controllers. 相似文献
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《Journal of Nuclear Science and Technology》2013,50(3):263-273
There has been increasing necessity for load following and/or AFC (Automatic Frequency Control) operation along with the growth in the share of nuclear power generation in the electric power network. Fuzzy logic control was investigated for application to a BWR recirculation flow control system, in order to obtain a rapid generator power response within an allowable neutron flux overshoot. The proposed controller has two control loops, generator power and neutron flux loop. The fuzzy logic is utilized for weighing these control loops and for controlling the neutron flux. By evaluating the controller performance by numerical simulations on the step response for generator power demand with the model BWR recirculation flow system, more rapid response was obtained than that for conventional proportional plus integral controllers with no neutron flux overshoot beyond alarm activation level. 相似文献
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Steam Generator (SG) is a crucial component of nuclear power plant. The proper water level control of a nuclear steam generator is of great importance in order to secure the sufficient cooling source of the nuclear reactor and to prevent damage of turbine blades. The water level control problem of steam generators has been a main cause of unexpected shutdowns of nuclear power plants which must be considered for plant safety and availability. The control problem is challenging, especially at low power levels due to shrink and swell phenomena and flow measurement errors. Moreover, the dynamics of steam generator vary as the power level changes. Therefore, it is necessary to improve the water level control system of SG. In this paper, an adaptive estimator-based dynamic sliding mode control method is developed for the level control problem. The proposed method exhibits the desired dynamic properties during the entire output tracking process independent of perturbations. Simulation results are presented to demonstrate the effectiveness of the proposed controller in terms of performance, robustness and stability. Simulation results confirm the improvement in transient response obtained by using the proposed controller. 相似文献
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Hengliang Shen 《Nuclear Engineering and Design》2009,239(6):1056-1065
In current generation pressurized water reactors (PWRs), the control of steam generator level experiences challenges over the full range of plant operating conditions. These challenges can be particularly troublesome in the low power range where the feedwater is highly subcooled and minor changes in the feed flow may cause oscillations in the SG level, potentially leading to reactor trip. The IRIS reactor concept adds additional challenges to the feedwater control problem as a result of a steam generator design where neither level or steam generator mass inventory can be measured directly.Neural networks have demonstrated capabilities to capture a wide range of dynamic signal transformation and non-linear problems. In this paper a detailed engineering simulation of plant response is used to develop and test neural control methods for the IRIS feedwater control problem. The established neural network mass estimator has demonstrated the capability to predict the steam generator mass under transient conditions, especially at low power levels, which is considered the most challenging region for a full range feed water controller. 相似文献
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Poor control of U-tube steam generators (UTSG) in a nuclear power plant can lead to frequent reactor shutdowns or damage of turbine blades. The steam generator is a highly complex, non-linear and time-varying system and its parameters vary with operating conditions. Therefore, it seems that design of a suitable controller is a necessary step to enhance plant availability factor. In this paper, a data-driven controller approximated by set membership approach is presented for the water-level control of U-tube steam generators in nuclear power plants. This controller is capable of learning the control action principles from the data obtained using other methods of automatic or manual control. Simulation results of the approximated controller demonstrate its capability in regulating the water level under random disturbances and reference level changes. 相似文献
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A neurofuzzy logic controller (NFLC), which is implemented by using a multilayer neural network with special types of fuzzifier, inference engine and defuzzifier, is applied to the water level control of a nuclear steam generator (SG). This type of NFLC has the structural advantage that arbitrary two-input, single-output linear controllers can be adequately mapped into a set of specific control rules of the NFLC. In order to design a stability-guaranteed NFLC, the stable sector of the given linear gain is obtained from Lyapunov's stability criteria. Then this sector is mapped into two linear rule tables that are used as the limits of NFLC control rules. The automatic generation of NFLC rule tables is accomplished by using the back-error-propagation (BEP) algorithm. There are two separate paths for the error back propagation in the SG. One considers the level dynamics depending on the tank capacity and the other takes into account the reverse dynamics of the SG. The amounts of error back propagated through these paths show opposite effects in the BEP algorithm from each other for the swell-shrink phenomenon. Through computer simulation it is found that the BEP algorithm adequately generates NFLC rule tables according to given learning parameters. 相似文献
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Auto-tuned PID controller using a model predictive control methodfor the steam generator water level 总被引:1,自引:0,他引:1
Man Gyun Na 《IEEE transactions on nuclear science》2001,48(5):1664-1671
In this paper, proportional-integral-derivative (PID) control gains are automatically tuned by using a model predictive control (MPC) method. The MPC has received much attention as a powerful tool for the control of industrial process systems. An MPC-based PID controller can be derived from the second-order linear model of a process. The steam generator is usually described by the well-known fourth-order linear model, which consists of the mass capacity, reverse dynamics, and mechanical oscillation terms. However the important terms in this linear model are the mass capacity and reverse dynamics terms, both of which can be described by a second-order linear system. The proposed auto-tuned PID controller was applied to a linear model of steam generators. The parameters of a linear model for steam generators are very different according to the power levels. The PID gains of the proposed controller are tuned automatically. Also, the proposed controller showed fast water level tracking and small shrink and swell performance by changing only the input-weighting factor according to the power level for the water-level deviation and sudden steam flow disturbances supposed to investigate the tracking performance and swell and shrink characteristics 相似文献
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In this paper, a P controller with partial feed forward compensation and decoupling control for the steam generator water level is presented. While taking the steam flowrate as a disturbance to water level, the controller design can be completed in three stages. (1) Main circuit controller is designed without regard to disturbance. Since the transfer function of the steam generator model contains integrate element and differential element, the proportional (P) controller can selected as main circuit controller instead of PID controller for steam generator water level. (2) Partial feed forward compensation is introduced to remove the disturbance from the steam flowrate. If disregarding the differential element, the partial feed forward compensation's designing turns to be very simple. Partial feed forward compensation coefficient is set as reciprocal of P controller gain. (3) The coupling effects between the water level regulating and steam flowrate disturbance can be decreased by model reference decoupling control. The proposed methodology shows satisfactory transient responses, disturbance rejection and robustness. 相似文献
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蒸汽发生器在瞬态扰动时存在严重的虚假水位现象,增加了低功率水位控制的难度。为研究蒸汽发生器低功率水位控制问题,利用线性参数变化理论,建立了时变的多胞线性参数变化模型。在此模型基础上,提出了分数阶控制器。依据分数阶微积分理论,设计了串级分数阶PIλDμ控制器。根据Oustaloup间接离散化方法实现了分数阶PIλDμ控制并对Oustaloup方法进行了改进。研究了在负荷变化时,内环和外环4个阶次参数以及改进算法后2个参数变化对系统控制性能的影响。在不同功率区间,相同负荷变化的情况下,对改进后的串级分数阶PIλDμ控制器进行了仿真实验。结果表明,所设计的改进串级分数阶PIλDμ控制器能有效抑制干扰,分数阶微积分算子的阶次以及改进的Oustaloup方法引入的系数对控制效果均有一定影响,合理调节参数能明显改善系统的控制性能。 相似文献
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为了进一步提高核动力装置的动态控制性能,本文在核动力装置汽轮机和直流蒸汽发生器数学模型的基础上,将基于模糊模型的多变量非线性广义预测控制算法应用于核动力装置主要参数的控制中,包括控制结构和控制器设计。仿真结果显示,当核动力装置负荷的工况变化时,多变量模糊预测控制律下汽轮机相对转速和蒸汽发生器出口压力变化响应时间较经典PID控制律下的快,而PID控制律下的相对转速较多变量模糊预测控制律下的多出3%~5%的超调。由此表明,所采用的多变量模糊预测控制算法能较好地控制核动力装置主要参数的输出,可获得较好的控制效果。 相似文献
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压水堆负荷跟踪的模糊控制系统 总被引:7,自引:4,他引:3
模糊控制理论的发展促进了模糊控制器在压水堆负荷跟踪中的应用。用模糊逻辑控制器和常规PID(比例-积分-微分)控制器相结合,并以输出增闪随功率调整的策略,解决了反应堆负荷跟踪问题,本方法解决了时变非线性对象的闭环控制并克服了基于模型的控制方法的不足,仿真结果显示本文提出的方案不但具有优良的动态特性,而且具有很高的稳态精度,使负荷跟踪控制的自动化程度大为提高。 相似文献