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《核电子学与探测技术》2017,(5)
本文结合ACPR1000核电站棒控棒位系统国产化研制情况,从逻辑功能设计、通信设计等方面介绍了一种棒控系统电流定值检测子系统的设计方案。相比于传统方案,该设计采用了FPGA技术,具有集成度高、灵活性高等优点。 相似文献
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广东岭澳核电二期工程数字化棒控棒位系统设计 总被引:6,自引:3,他引:3
广东岭澳核电二期工程控制棒控制系统和控制棒棒位监测系统(以下简称棒控棒位系统)采用基于法国AREVA的安全级仪控平台TXS技术和数字化技术,以及冗余设计技术手段,实现了反应堆温度和功率的集中控制.采用大功率晶体管实现了对控制棒的"一带一"控制;采用分组编码探测器对控制棒在堆芯中的位置进行监测.本文对其设计要求和设计特点进行了介绍,并将没计结果与岭澳核电一期和秦山二期棒控棒位系统的设计结果进行了比较.结果表明,岭澳二期的棒控棒位系统能为运行人员和维护人员提供丰富的信息,方便了系统的运行和维护,提高了系统的可靠性. 相似文献
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《核电子学与探测技术》2018,(3)
本文对核电仪控系统的核心控制单元中使用的IGBT功率模块进行散热设计符合性论证和验证。建立IGBT热阻分析模型,结合核电产品不同运行工况,计算各种工况下的工作电流,根据计算的工作电流计算不同工况的温升。对功率模块实际温升进行测试和验证。从理论计算和实际测试两个角度分别进行分析和验证。分析和验证结果表明:该控制系统中的IGBT热设计合理,满足棒控系统在各种工况下的工作需求。 相似文献
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卢才华 《核电子学与探测技术》2004,24(2):209-211
简单介绍了棒控系统在核电站的作用,着重介绍了棒控系统调试、运行过程中发现的主要问题及提高可靠性的改进措施.对改进效果作了简要评价。 相似文献
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秦山核电一期棒控棒位系统经数字化改造后,采用PLC(programmable logic controller)(现逻辑控制功能,建立人机界面对系统状态进行在线监测和授权参数修改,控制部分采用冗余配置,提高了系统的灵活性和可靠性;对模拟电路进行修改,采用故障双保持的电路设计;控制棒控制系统和棒位指示系统间通过冗余配置的... 相似文献
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秦山一期核电厂300 MW反应堆功率棒控棒位系统为模拟仪表控制系统,由于设备老化、维护困难和可靠性下降等原因需要改造.系统改造采用基于CPU冗余、电源冗余和ControlNet现场总线冗余的控制方案.利用PLC控制技术,对其棒控棒位模拟仪表控制系统进行数字化改造设计,克服了系统参数不能实时调整、抗干扰能力差等缺陷,增强了系统的通信能力、集中监控能力及系统可维护性,提高了系统的可靠性和安全性.模块化的程序设计,增强了程序的可读性和实用性,减少了程序扫描时间,保证了系统响应速度.实际反应堆的运行效果验证了设计的合理性. 相似文献
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《Fusion Engineering and Design》2014,89(3):165-176
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. 相似文献
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建立标准氡室的关键是对测量环境的温度、湿度和风速进行严格控制.本文介绍了某标准氡室自动监控系统的控制原理、软硬件结构和系统设计思想.该监控系统实现了氡室的温湿度自动控制、氡及氡子体浓度的自动检测和实验测量过程的数据全程记录.运行结果表明,该系统使用效果良好,达到了预期的设计目的. 相似文献
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为了对质子照相束流线设备进行远程监测与控制,实现束流线各子系统的安全联锁功能,研制了一套采用标准控制模型结构的分布式EPICS控制系统。该控制系统通过PLC组态实现了开关逻辑设备的安全联锁及工艺流程控制。核心控制系统采用EPICS建立了多个IOC作为控制器。针对不同CPU构架下的服务器搭建了交叉编译环境。针对数字电源设备与真空仪表设备使用StreamDevice完成设备驱动及通信协议的开发,并通过建立IOC动态数据库,实现了IOC对流设备和PLC信号的监测与控制功能。使用CSS设计OPI,实现了上位机对EPICS IOC中数据的透明访问。该束流线控制系统已成功应用于CYCIAE-100回旋加速器的质子照相物理实验中。通过长时间的运行,控制系统的可靠性、安全性得到了验证。控制系统的稳定运行,为质子照相实验的开展奠定了基础,对类似的控制系统研制具有一定的参考价值。 相似文献
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The design of the control system for radial plasma position on HL-2A based on model reference adaptive control (MRAC) principle is presented in this paper. The simulated results show that it can be used to improve the performance of the system greatly. Compared with the classical PID control system, it has obvious advantages in the better dynamic response, the smaller quantity of calculation and the better robustness. 相似文献
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介绍了一个基于Windows CE的嵌入式分布控制系统,系统基于以太网和现场总线连接,节点用嵌入式平板计算机实现。给出了系统的硬件组成和软件设计,该系统已应用于HIRFL-CSR前端控制系统。 相似文献
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《Fusion Engineering and Design》2014,89(3):267-272
ITER will be the world's largest magnetic confinement tokamak fusion device and is currently under construction in southern France. The ITER Plasma Control System (PCS) is a fundamental component of the ITER Control, Data Access and Communication system (CODAC). It will control the evolution of all plasma parameters that are necessary to operate ITER throughout all phases of the discharge. The design and implementation of the PCS poses a number of unique challenges. The timescales of phenomena to be controlled spans three orders of magnitude, ranging from a few milliseconds to seconds. Novel control schemes, which have not been implemented at present-day machines need to be developed, and control schemes that are only done as demonstration experiments today will have to become routine. In addition, advances in computing technology and available physics models make the implementation of real-time or faster-than-real-time predictive calculations to forecast and subsequently to avoid disruptions or undesired plasma regimes feasible. This requires the PCS design to be adaptable in real-time to the results of these forecasting algorithms. A further novel feature is a sophisticated event handling system, which provides a means to deal with plasma related events (such as MHD instabilities or L-H transitions) or component failure. Finally, the schedule for design and implementation poses another challenge. The beginning of ITER operation will be in late 2020, but the conceptual design activity of the PCS has already commenced as required by the on-going development of diagnostics and actuators in the domestic agencies and the need for integration and testing. This activity is presently underway as a collaboration of international experts and the results will be published as a subsequent publication. In this paper, an overview about the main areas of intervention of the plasma control system will be given as well as a summary of the interfaces and the integration into ITER CODAC (networks, other applications, etc.). The limited amount of commissioning time foreseen for plasma control will make extensive testing and validation necessary. This should be done in an environment that is as close to the PCS version running the machine as possible. Furthermore, the integration with an Integrated Modeling Framework will lead to a versatile tool that can also be employed for pulse validation, control system development and testing as well as the development and validation of physics models. An overview of the requirements and possible structure of such an environment will also be presented. 相似文献
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《Fusion Engineering and Design》2014,89(5):512-517
The plasma control system is a key instrument for successfully investigating the physics of burning plasma at ITER. It has the task to execute an experimental plan, known as pulse schedule, in the presence of complex relationships between plasma parameters like temperature, pressure, confinement and shape. The biggest challenge in the design of the control system is to find an adequate breakdown of this task in a hierarchy of feedback control functions. But it is also important to foresee structures that allow handling unplanned exceptional situations to protect the machine. Also the management of the limited number of actuator systems for multiple targets is an aspect with a strong impact on system architecture. Finally, the control system must be flexible and reconfigurable to cover the manifold facets of plasma behaviour and investigation goals.In order to prepare the development of a control system for ITER plasma operation, a conceptual design has been proposed by a group of worldwide experts and reviewed by an ITER panel in 2012. In this paper we describe the fundamental principles of the proposed control system architecture and how they were derived from a systematic collection and analysis of use cases and requirements. The experience and best practices from many fusion devices and research laboratories, augmented by the envisaged ITER specific tasks, build the foundation of this collection. In the next step control functions were distilled from this input. An analysis of the relationships between the functions allowed sequential and parallel structures, alternate branches and conflicting requirements to be identified. Finally, a concept of selectable control layers consisting of nested “compact controllers” was synthesised. Each control layer represents a cascaded scheme from high-level to elementary controllers and implements a control hierarchy. The compact controllers are used to resolve conflicts when several control functions would use the same command signals as their outputs. They consist of a collection of potentially conflicting control functions from which one at a time is exclusively activated by a mode selector signal.It can be shown that this architectural design is capable of implementing all of the presently known functional control requirements. Furthermore, this design takes already into account that the result of future experiments at ITER will create additional requirements on the functions or performance of ITER plasma control. 相似文献