蒸汽发生器双级模糊积分智能水位控制器设计

为了实现对蒸汽发生器水位的有效控制,设计了双级模糊积分智能水位控制器.在常规模糊控制器之前,增加了"假水位"判别模糊控制器,以实现在"假水位"阶段对水位进行有效控制.为实现对水位的最优控制,将模糊控制器和积分控制器结果协调输出.通过对控制响应曲线的分析,验证本论文所设计的双级模糊积分智能控制器能有效克服"假水位"现象对水位控制带来的不利影响,且控制超调量小,稳定时间短.     

稳压器水位控制改进研究

现代的反应堆稳压器的水位控制大都采用的是传统的PI调节器,对于这样一个非线性和时变性的复杂控制系统,PI调节器表现出来的常常是超调量大、调节时间长等并不理想的效果.本文提出以智能模糊控制器取代原有常规PI控制器的改进方案,并以大亚湾一期工程反应堆控制系统的稳压器水位控制为研究对象,着重阐述智能模糊控制原理在具体实践中的使用方法,最后对改造前后的系统输出进行LabVIEW仿真比较.仿真结果表明,模糊PI调节器不但克服了常规PI调节器的缺点,而且还提高了控制系统的实时性和抗干扰能力,值得广泛采用.     

状态微分反馈控制与压水反应堆功率现有两种控制系统的等价性研究

本文提出了一种新型的反馈控制--状态微分反馈控制,并用于设计负荷跟随运行模式下的反应堆控制系统。设计过程依赖于控制棒位置的积分控制和控制棒速度的状态微分反馈控制两种控制系统之间的等价性,这一关系被证明并总结为定理。数值仿真结果表明,所设计的反应堆功率的状态微分反馈控制系统具有很好的负荷跟随模式性能。     

Robust control design for the plasma horizontal position control on J-TEXT Tokamak

It is extremely important for tokamak to control the plasma position during routine discharge. However, the model of plasma in tokamak usually contains much of the uncertainty, such as structured uncertainties and unmodeled dynamics. Compared with the traditional PID control approach, robust control theory is more suitable to handle this problem. In the paper, we propose a H_∞ robust control scheme to control the horizontal position of plasma during the flat-top phase of discharge on Joint Texas Experimental Tokamak (J-TEXT) tokamak. First, the model of our plant for plasma horizontal position control is obtained from the position equilibrium equations. Then the H_∞ robust control framework is used to synthesize the controller. Based on this, an H_∞ controller is designed to minimize the regulation/tracking error. Finally, a comparison study is conducted between the optimized H_∞ robust controller and the traditional PID controller in simulations. The simulation results of the H_∞ robust controller show a significant improvement of the performance with respect to those obtained with traditional PID controller, which is currently used on our machine.     

压水堆棒控系统数字化设计

系统采用西门子S7-400 PLC进行系统的总体控制,采用PROFIBUS-DP网络进行系统的通讯,实现了棒控系统的数字化控制,并对棒控系统的硬件设计、软件设计以及系统的调试进行了研究。该系统设计新颖,技术先进,符合国际发展趋势,对国产核电站数字化仪控系统的出口具有现实意义。     

Fuzzy Logic Control Application for BWR Recirculation Flow Control System

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.     

用于加速器数字反馈控制研究的实验平台

本文介绍了用于加速器数字反馈控制研究的实验平台。该平台由四极磁铁、磁铁电源、Hall电路、DSP系统和用于系统开发的计算机组成。它不仅可用于加速器轨道反馈控制等系统级的研究,而且还可以用于研究高精度电源和高频系统低电平等设备级的数字反馈控制。     

非安全级优选控制技术在CPR1000核电工程中的应用

在CPR1000核电工程项目中存在着诸多参与安全功能的同时受1E和NC级DCS信号控制的非安全级设备,当1E和NC级命令同时到达时,需对1E和NC级DCS命令进行优选处理。本文提出一种优选控制技术,充分考虑不同信号优先级逻辑比较和1E级信号的定期试验回路设计。结果表明,非安全级优选控制技术通过了SL1和SL2抗震试验,为这类非安全级设备的不同级别的控制命令优选处理以及1E级命令的定期试验提供了解决方案。     

Overview of magnetic control in ITER

ITER is targeting Q = 10 with 500 MW of fusion power. To meet this target, the plasma needs to be controlled and shaped for a period of hundreds of seconds, avoiding contact with internal components, and acting against instabilities that could result in the loss of control of the plasma and in its disruptive termination.Axisymmetric magnetic control is a well-understood area being the basic control for any tokamak device. ITER adds more stringent constraints to the control primarily due to machine protection and engineering limits. The limits on the actuators by means of the maximum current and voltage at the coils and the few hundred ms time response of the vacuum vessel requires optimization of the control strategies and the validation of the capabilities of the machine in controlling the designed scenarios.Scenarios have been optimized with realistic control strategies able to guarantee robust control against plasma behavior and engineering limits due to recent changes in the ITER design. Technological issues such as performance changes associated with the optimization of the final design of the central solenoid, control of fast transitions like H to L mode to avoid plasma-wall contact, and optimization of the plasma ramp-down have been modeled to demonstrate the successful operability of ITER and compatibility with the latest refinements in the magnetic system design.Validation and optimization of the scenarios refining the operational space available for ITER and associated control strategies will be proposed. The present capabilities of magnetic control will be assessed and the remaining critical aspects that still need to be refined will be presented. The paper will also demonstrate the capabilities of the diagnostic system for magnetic control as a basic element for control. In fact, the noisy environment (affecting primarily vertical stability), the non-axisymmetric elements in the machine structure (affecting the accuracy of the identification of the plasma boundary), and the strong component of eddy current at the start-up (resulting in a poor S/N ratio for plasma reconstruction for I_p < 2 MA requiring a robust plasma control) make the ITER magnetic diagnostic system a demanding part of the magnetic control and investment protection systems. Finally the paper will illustrate the identified roles of magnetic control in the PCS (plasma control system) as formally defined in the recent first step of the design and development of the system.     

广义预测自校正控制算法在核反应堆功率控制中的应用研究

阐述了核反应堆堆芯的中子动力学数学模型,并应用该模型建立传递函数.提出将广义预测自校正控制算法应用于反应堆功率控制中,包括控制结构和控制器设计.仿真结果表明所采用的广义预测自校正控制算法能够较好地控制反应堆功率的输出,取得了较好的控制效果.     

Counter Comment to Dr. Kuznietz for his Comments

A differential-difference equation model is introduced which can describe the dynamics of any type of extractor, whether, mixer settler, pulsed column or rapid contactor.

The differential or difference equation models used by several investigators prove to be particular cases of this model. From the results calculated by this model, it is shown that there exist an optimal stage and an optimal component for monitoring the performance in the control of extractors.

A computer control system for the solvent extraction step of the Purex process is devised with use made of a generalized version of the classical cascade control law, which the authors have named the Multivariate Cascade Control Law.

This law can easily be extended for application to the control of the Purex process as a whole.     

大功率NBI系统的PLC时序控制应用

论述了利用PLC逻辑关系对放电实验控制运行的工作原理,介绍了PLC梯形图应用程序和VB6.0环境下上位机监控程序的开发以及良好的人机操作界面,通过上位机监控界面来实时监控各电源及设备的运行状态.PLC控制系统的应用保障了实验装置的安全运行,极大地方便了实验中对放电参数的改变和设置.     

包覆燃料颗粒制备的自动化控制系统设计与研制

针对高温气冷堆包覆燃料颗粒生产逐渐规模化大批量发展的趋势,原制备工艺的手动控制体系已不能适应,需发展现代化工业级别的包覆燃料颗粒制备自动化控制系统。针对TRISO型包覆燃料颗粒4层连续包覆工艺进行分析,将包覆炉系统划分为5个子系统,将整个包覆过程分解为9个操作状态,提出建立分布式控制系统（DCS）自动化控制系统的思路。根据对包覆颗粒制备工艺的严格要求提出了控制系统设计原则,包括连锁控制、安全可靠、集成规范、实用易用、开放和易更新原则,并在具体建设过程中实现了这些原则要求,建立起一套完整的包覆燃料颗粒制备工艺自动化控制系统。该系统在我国高温气冷堆示范工程项目辐照样品的生产中投入运行,经实践检验,证明该系统可较好地实现包覆燃料颗粒制备工艺控制,满足工厂规模的生产要求。     

Strike Point Control on EAST Using an Iso?ux Control Method

For the advanced tokamak, the particle deposition and thermal load on the divertor is a big challenge. By moving the strike points on divertor target plates, the position of particle deposition and thermal load can be shifted. We could adjust the Poloidal Field (PF) coil current to achieve the strike point position feedback control. Using isoflux control method, the strike point position can be controlled by controlling the X point position. On the basis of experimental data, we establish relational expressions between X point position and strike point position. Benchmark experiments are carried out to validate the correctness and robustness of the control methods. The strike point position is successfully controlled following our command in the EAST operation.     

箱包DR-CT检测系统断层定位控制设计

简要介绍了箱包DR-CT检测系统的原理,分析了控制子系统的功能,并详细介绍了控制子系统断层定位PID控制方案设计及其参数整定方法。基于PID控制的控制子系统大大减小了定位误差,其断层定位精度满足设计目标和要求。     

大型集装箱CT检测系统PID控制设计

简要介绍了大型集装箱CT检测系统的原理及其控制系统结构,分析了PID控制系统的组成,并详细介绍了PID控制算法和参数整定方法.系统的实际运行结果表明,选择合适参数的PID控制满足检测系统响应速度快、定位精度高的要求.     

核电厂控制室控制功能切换方案研究

核电厂为运行人员提供了主控制室（MCR）作为电厂集中监控中心,并提供了与MCR实体隔离和电气隔离的远程停堆站（RSS）作为辅助控制室,以在MCR不可用时投入使用,对电厂实施监控,并将电厂带入停堆状态和导出余热。根据核安全法规、导则及标准要求,来自MCR和来自RSS的电厂控制功能须相互闭锁,不能同时执行。本文通过比较分析,研究CPR1000、EPR及AP1000堆型核电厂控制室操作模式切换方案的特点与不足,在详细研究的基础上给出控制室切换功能设计的几个基本原则,供新的核电厂控制室功能切换方案设计时参考,以设计出更为实用、简洁、安全、便利的方案。     

陶瓷UO_2微球尺寸与球度的控制方法

陶瓷ＵＯ２微球尺寸与球度的控制问题，不仅是溶胶－凝胶工艺研究中的重要课题，也是高温气冷堆燃料元件生产中的重要课题。因此，近几年来通过批量试验对全胶凝工艺控制包覆芯核尺寸与球度的方法进行了研究，并取得了阶段性进展，为１０ＭＷ高温堆燃料芯核的生产奠定了基础。结果表明：ＵＯ２芯核尺寸与球度的控制主要是通过控制溶胶分散参数来实现的。对单一振动喷嘴而言，其分散参数应当同时满足均匀分散流量方程和振动频率方程的要求；另一方面为了控制芯核的球度，还必须对喷嘴的振动加速度、３区高度及气相氨的分布进行控制。     

Development of real-time plasma analysis and control algorithms for the TCV tokamak using Simulink

One of the key features of the new digital plasma control system installed on the TCV tokamak is the possibility to rapidly design, test and deploy real-time algorithms. With this flexibility the new control system has been used for a large number of new experiments which exploit TCV's powerful actuators consisting of 16 individually controllable poloidal field coils and 7 real-time steerable electron cyclotron (EC) launchers. The system has been used for various applications, ranging from event-based real-time MHD control to real-time current diffusion simulations. These advances have propelled real-time control to one of the cornerstones of the TCV experimental program. Use of the Simulink graphical programming language to directly program the control system has greatly facilitated algorithm development and allowed a multitude of different algorithms to be deployed in a short time. This paper will give an overview of the developed algorithms and their application in physics experiments.