CSRe团簇内靶温度闭环控制器设计

介绍了国家重大科学工程项目——兰州重离子加速器冷却存储环(HIRFL-CSR)的实验环(CSRe)团簇内靶温度闭环控制器的设计。该控制器给气体喷嘴处测温电阻提供长时间稳定度为0.1%的1mA恒定电流,通过12位ADC得到喷嘴温度,并通过混合信号处理器MSP430F149来实现制冷/加热闭环操作。在多种不同实验气体的情况下,该控制器的温度控制精度小于0.5K。目前,该控制器在现场工作良好。     

CYCIAE-100回旋加速器测磁仪自动控制系统的研制

为满足100 MeV回旋加速器磁场测量要求,设计研制了一套测磁仪自动化控制装置。该装置采用周向与径向相结合的运动方式,对目标点磁场进行测量。周向运动采用开环控制,在软件上通过算法实现间接闭环控制,整个测磁过程,只需完成1次周向运动,缓解了由硬件原因带来的周向定位震荡问题。径向运动基于光栅位置反馈,由运动控制器实现自动闭环控制,该方案使角度精度达到±5″以内,径向精度达±5 μm,达到并优于理论设计要求,解决了中能回旋加速器磁场测量时间较长、精度低的难题,对100 MeV回旋加速器的束流强度及品质的提高有重要意义。     

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.     

Active oxygen control by a PbO mass exchanger in the liquid lead–bismuth eutectic loop: MEXICO

Accurate control of dissolved oxygen concentration is crucial in order to use liquid lead alloys as a coolant of advanced nuclear systems. An oxygen control system based on PbO mass exchanger (PbO MX) technology was implemented in order to control the dissolved oxygen concentration in the liquid lead--bismuth eutectic (LBE) loop MEXICO. The oxygen control system consisted of a packed bed of PbO spheres, an oxygen sensor and a pneumatic control valve. The concentration of dissolved oxygen in the loop was controlled by regulating the LBE flow through the PbO MX using a proportional–integral–derivative (PID) controller with feedback from the oxygen sensor. Highly accurate control of the dissolved oxygen concentration in the loop was achieved by this system.     

Computer Control System for Sodium Test Loops

A digital computer system was developed for automatic operation of the Toshiba Sodium Test Loops, intended for studying the control system of liquid metal fast breeder reactors.

The test installation is controlled by a system of two TOSBAC-40C central processing units, which take care of plant monitoring, data logging, information display, sequence control and closed loop control. The operator console linked to the computers can handle more than 3,000 process input/output signals. The state of the plant and measured data are displayed on two color cathode-ray tube installed on the console. Normal operation of the four loops constituting the installation can be supervised by one single operator.

Safety in the case of power failure and other emergencies is assured by a safety protection system that functions independently of the computer system.     

鲁棒PID控制器的H∞回路成形优化设计及其在蒸汽发生器水位控制中的应用

针对H_∞回路成形设计,提出了一种基于线性矩阵不等式技术的PID型权函数优化算法。结合静态H_∞回路成形控制器综合,给出了一种系统的鲁棒PID迭代优化方法。基于所提方法设计了蒸汽发生器水位控制系统的PID型主控制器。仿真结果表明,所设计控制系统具有较好的鲁棒性能和鲁棒稳定性,综合控制品质优于全阶权函数优化（或本文所提PID型权函数优化）和标准控制器综合相结合的方法。     

核电站仪控系统数字化开发仿真测试技术研究

在核电站应用数字化仪表与控制 (I&C)取代模拟 I&C 系统,已成为必然的发展趋势。本文分析了核电站全范围模拟机的蒸汽发生器数学模型,研制开发独立的核电站蒸汽发生器实时仿真系统,并与控制系统形成能够相互作用的闭环系统,用于数字化仪控系统改造提供仿真对象及进一步控制方案研究。在仿真过程中,除了仿真模型之外,其他的硬件和软件由真实的控制系统构成。不但为核电站仪表与控制 (I&C)系统数字化开发提供理论分析,也为今后现场调试工作创造有利条件。     

反应堆功率保成本控制器设计

针对反应堆功率控制系统设计中存在的建模误差以及实际运行过程中参数的不确定性,提出了一种新的功率保成本鲁棒控制器设计方法:运用线性矩阵不等式先求解出最优状态反馈保成本控制器,构造卡尔曼滤波器解决实际问题中状态不可测的问题,采用回路恢复的方法使总系统逼近目标反馈环传递函数.系统仿真结果表明,所设计的控制器实现了对设定功率的精确跟踪,解决了在堆模型不确定性、运行过程中参数不确定性下控制系统可能出现的不稳定和控制精度不够的问题,系统不但具有良好的鲁棒性,而且调节性能较好,满足堆功率调节控制的要求.     

HLS800MeV直线加速器相位控制系统的研制

介绍了合肥光源(HLS)800 MeV直线加速器相位控制系统的研制进展,该系统包括相位稳定系统和相位翻转系统两部分。其中前者主要由I/Q解调器、电控移相器和虚拟示波器等组成;后者由脉冲信号发生器和I/Q调制器组成。目前样机制作已完成,测试表明前者的相位分辨率为±0.1°,在线测量精度为±0.3°,闭环相位稳定度可达±0.5°;后者的精度为(180±2)°,样机各项参数均达到设计指标。     

压水堆核电厂蒸汽排放控制系统实时仿真研究

建立了压水堆核电厂蒸汽排放控制系统及其控制对象的实时仿真模型,包括蒸汽发生器及相关管道阀门的数学模型.在此模型基础上,编制了压水堆核电厂蒸汽排放控制系统动态特性的实时仿真程序,并对该控制系统模型进行了闭环稳态和瞬态等工况的可视化动态实时仿真.仿真结果表明,程序输出与实际系统响应趋势一致,仿真软件能实时输出蒸汽排放控制系...     

棒位探测器电源系统比例复数积分控制策略研究

单相逆变器在核电厂棒位检测系统中工作于电压源模式,其负载棒位探测器通常等效为阻感性负载,而阻感性负载连接至逆变器输出端不能稳定地输出正弦电压。为此,本文针对单相逆变器棒位探测器电源系统提出了一种比例复数积分（PCI）控制策略,并给出控制器参数设计方法。首先,基于系统的频域模型推导出电流环比例积分（PI）控制器和电压环PCI控制器参数解析式,并考虑负载参数对系统稳定性的影响。然后,设定期望的电流环和电压环开环截止频率和相位裕度,通过本文方法解析计算PI和PCI控制器参数。最后,通过MATLAB仿真验证了本文方法能够使阻感性负载下的单相逆变器得到稳定的输出电压与输出电流,且输出电流谐波畸变率（THD）<0.3%。该方法可以为单相逆变器棒位探测器电源系统控制提供指导。     

High performance plasma vertical position control system for upgraded MAST

A plasma vertical control system able to control high elongation (～2.5) plasmas at moderate internal inductance (～0.9) is analysed, including both active and passive components in a closed loop system. The analysis is based on the RZIp rigid plasma model and this is extensively validated using present day MAST discharges, especially at the limits of controllability. Special consideration is given to the unusual MAST geometry (coils inside the main vacuum vessel) and general conclusions regarding system design are drawn wherever possible.     

A novel testing approach for SSRF digital power supply controllers

Digital power supply controller is one of the key parts of SSRF high resolution high stability magnet power supply system.It is very essential to keep any degradation of these excellent properties by any stages as small as possible via careful testing when the controller is developed.In this study,a novel testing approach was presented,with which a novel closed conrail loop without actual power converter was constructed,and the new developed SSRF Digital Controller can work well in it.     

基于H∞回路成形方法的蒸汽发生器水位控制系统主控制器参数整定

针对U形管蒸汽发生器水位前馈 反馈串级三冲量控制系统的主控制器PID参数整定困难,且鲁棒性要求高的特点,给出了一种基于H_∞回路成形方法的主控制器PID参数整定方案。在负荷变化情况下,对采用传统方案整定主控制器的PID参数和H^∞回路成形方法整定主控制器的PID参数蒸汽发生器水位控制系统进行了对比仿真实验。仿真结果表明,采用该方法整定的控制系统具有良好的鲁棒稳定性和较好的控制性能。     

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.     

Suboptimal Control of Pressurized Water Reactor Power Plant Using Approximate Model-Following Method

We attempted to develop an effective control system that can successfully manage the nuclear steam supply (NSS) system of a PWR power plant in an operational mode requiring relatively small variations of power. A procedure is proposed for synthesizing control system that is a simple, yet practiced, suboptimal control system. The suboptimal control system is designed in two steps; application of the optimal control theory, based on the linear state-feedback control and the use of an approximate model-following method. This procedure can appreciably reduce the complexity of the structure of the controller by accepting a slight deviation from the optimality and by the use of the output-feedback control. This eliminates the engineering difficulty caused by an incompletely state-feedback that is sometimes encountered in practical applications of the optimal state-feedback control theory to complex large-scale dynamical systems. Digital simulations and graphical studies based on the Bode-diagram demonstrate the effectiveness of the suboptimal control, and the applicability of the proposed design method as well.     

A New Method for Low Sensitivity Design of a Controller for a Load Following BWR Power Plant

A new method has been proposed in which the controller is approximated by two low order models, the second being the sensitivity model of the first. Thus a Kind of piecewise solution is proposed in which the system retains the same order irrespective of the number of parameters to be considered for low sensitivity design. The usefulness of the proposed technique is illustrated in the controller design for a direct cycle BWR power plant of 457 MW(thermal) with recirculation control. The mathematical model includes the reactor kinetics, hydrodynamics of the recirculation loop, pressure transients, and the load frequency control system. The response of system variables such as frequency, neutron power, and reactor pressure are plotted with the low sensitivitty controller. The sensitivity function of frequency has been plotted using the conventional and proposed low sensitivity controller for 20 per cent variation in parameter values. The method is specifically recommended for controller design of large size systems.     

Control of Repetitive-Accelerator Fast-Pulsed Reactor

Control algorithms are proposed for on-line computer control of the repetitive-accelerator fast-pulsed reactor.

Firstly, simplification of the reactor core dynamics is obtained by regression analysis technique in order to obtain a compact model of the pulsed reactor.

Secondly, a start-up control algorithm to avoid severe thermal shock in the fuel rod is proposed. This is essentially a programmed control, whereby the external neutron source from the accelerator and the external reactivity are controlled in such manner that the fuel temperature would follow a predetermined time trajectory. Applicability of the method to the reactor start-up is proved by a computer simulation experiment.

Thirdly, a control concept for constant power operation is proposed. This is composed of two control loops: (1) a fine control loop, which responds quickly to small variations of reactor power, and (2) a diagnosis and adaptation loop, which judges whether a large deviation from set-up value observed on the reactor power output is due to an abnormality in the external neutron source, or to a change of the set-up value itself, and then adaptively returns the reactor power to the set-up value. A computer simulation experiment demonstrated the validity of the control system characteristics.

A discussion is also presented on the problems foreseen in applying the proposed methods to the actual design of a digital computer control system.     

320 kV全离子综合实验平台控制系统升级

本文对320 kV全离子综合实验平台的控制系统升级进行了研究。升级后的控制系统采用分布式系统模型构建。硬件采用串口服务器、PLC及伺服电机等部件实现了所有被控设备的远程监测及控制。软件通过建立EPICS IOC动态数据库,实现了对所有被控设备的集成。用户操作界面层采用CSS开发,实现了操作人员对所有被控设备的透明访问。该控制系统已成功连续运行约10 000 h。目前该控制系统运行稳定、可靠,完全满足320 kV全离子综合实验平台的运行及物理实验的需求。