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压水堆核动力厂控制系统可视化模化与仿真软件——NCS 总被引:1,自引:0,他引:1
《中国核科技报告》1999,(1)
对压水堆核动力厂控制系统的建模与仿真进行了较系统的研究。提出了用于压水堆核动力厂控制系统快速和精确仿真的被控对象数学模型和数值方法。被控对象模型主要包括堆芯、稳压器、蒸汽发生器、管道及泵的模型等,分别采用了龙格-库塔法和特雷纳方法求解这些模型。设计了面向控制系统结构图的可视化模化平台,实现了图形方式下的控制系统可视化建模,并采用离散相似法对所建立的控制系统数学模型进行求解。研制出了相应的压水堆核动力厂控制系统可视化模化与系统仿真软件——NCS,并用NCS软件对商用核电站控制系统进行了仿真研究,得到了满意的结果。NCS软件对核电站控制系统设计和分析研究工作具有很好的参考和实用价值。 相似文献
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核电站的控制区出入控制系统承担着人员进出控制、物件进出控制 ,防止污染扩散等重要功能。在 IRPA-1 0会议期间了解了国外核电站出入控制系统的改进和发展。通过介绍日本福岛 ( Fukushima)核电站出入控制系统的改进 ,并结合秦山核电站控制区出入控制系统的改进和优化进行比较 ,谈一些评价意见。 相似文献
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核电站的控制区出入控制系统承担着人员进出控制、物件进出控制、防止污染扩散等重要功能。在IRPA-10会议期间了解了国外核电站出入控制系统的改进和发展。通过介绍日本福岛(Fudushima)核电站出入控制系统的改进,并结合秦山核电站控制区出入控制系统的改进和优化进行比较,谈一些评价意见。 相似文献
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核电站的控制区出入控制系统承担着人员进出控制、物件进出控制,防止污染扩散等重要功能。在IRPA-10会议期间了解了国外核电站出入控制系统的改进和发展。通过介绍日本福岛(Fukushima)核电站出入控制系统的改进,并结合秦山核电站控制区出入控制系统的改进和优化进行比较,谈一些评价意见。 相似文献
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在核电站正式投入运行前,必须对各控制系统分别进行调试,验证系统的稳定性,并使其具有良好的动态品质和稳态精度.对控制系统进行调试,需要根据控制系统静态和瞬态仿真计算的结果,提供系统的参数整定值.因此在秦山核电二期工程控制系统的设计中引入了现代计算机仿真技术.在整个核电站基本参数已经确定的基础上,结合理论分析,主要以国外通用的用于核电站控制系统仿真设计的计算机仿真程序CATIA2为工具进行了一系列仿真实验,通过改变控制参数并分析所得仿真实验结果,最后确定出了一套合理的控制参数,为电站开堆调试和实际运行作了必要的准备. 相似文献
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介绍了中国实验快堆及三废系统的组成和必要性,国内商用核电站三废系统运行情况。介绍国家标准、法规对核电站三废系统设计的要求,对三废系统贮存、排放废气、废液的要求。利用图形方式介绍中国实验快堆的三废控制系统功能和结构特点。 相似文献
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核电站控制系统的数字化和联网化,在提高控制性能、方便操作维护的同时,也带来新的安全漏洞。特别是通用的协议、软件和设备正逐步取代原有的专用系统,这导致系统安全漏洞更容易被利用。而控制系统与现实世界直接相互作用,一旦出现安全问题,将威胁人身健康和环境安全,破坏关键基础设施,甚至危及国家安全。通过详细评述近年来数起与核电相关的控制系统安全事件,总结归纳控制系统安全的重要意义和难点问题。结合现有的研究成果,分析展望了有学术价值的研究方向。 相似文献
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The digitalized Instrumentation and Control (I&C) system of Nuclear power plants can provide more powerful overall operation capability, and user friendly man-machine interface. The operator can obtain more information through digital I&C system. However, while I&C system being digitalized, three issues are encountered: (1) software common-cause failure, (2) the interaction failure between operator and digital instrumentation and control system interface, and (3) the non-detectability of software failure. These failures might defeat defense echelons, and make the Diversity and Defense-in-Depth (D3) analysis be more difficult. This work developed an integrated methodology to evaluate nuclear power plant safety effect by interactions between operator and digital I&C system, and then propose improvement recommendations. This integrated methodology includes component-level software fault tree, system-level sequence-tree method and nuclear power plant computer simulation analysis. Software fault tree can clarify the software failure structure in digital I&C systems. Sequence-tree method can identify the interaction process and relationship among operator and I&C systems in each D3 echelon in a design basis event. Nuclear power plant computer simulation analysis method can further analyze the available backup facilities and allowable manual action duration for the operator when the digital I&C fail to function. Applying this methodology to evaluate the performance of digital nuclear power plant D3 design, could promote the nuclear power plant operation safety. The operator can then trust the nuclear power plant than before, when operating the highly automatic digital I&C facilities. 相似文献
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文章通过对国产核电机组"华龙一号"外围厂房除盐水生产系工艺流程的描述,介绍了西门子S7-400系列PLC在"华龙一号"除盐水控制系统的设计原则、软硬件配置、系统组态方式方法等,阐述了一种可编程控制器在新建核电领域中的应用实例。相对于DCS(分散控制系统)大而广的控制特点,PLC将以其专业化、小型化等特点在核电控制领域独树一帜,推动核电控制领域技术发展。 相似文献
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文章简述了核电仪控安全系统数字化的发展背景,分析了美国核管会(NRC)等核安全当局针对软件共因故障(SWCCF)的观点。针对核电安全系统采用数字化平台后,引入的软件共因故障问题,以方家山核电工程安全系统数字化的设计方案为例,阐述了计算机软、硬件多样性的防范策略,在软件共因故障防御的问题上,为核电数字化安全系统提供了一种多样性纵深防御的解决方案;同时分析了核安全执照申请中可能遇到的问题,并提出未来核电安全仪控系统可能的发展方向。 相似文献
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为保证国产化的核电厂集散控制系统(DCS)的安全性和可靠性,必须对其实施验证和确认(V&V)过程.为使V&V过程顺利进行,建立适用的V&V体系是十分必要的.本文提出了V&V体系的建立,该体系包括:明确具有层级关系的V&V指导文件;定义支持DCS研发生命周期的V&V过程;指定DCS软件完整性等级的划分方案以及确定V&V独立性、人员资质和工具的要求.该V&V体系适用于核电厂DCS软件研发项目,并对促进自主化开发和取证工作具有非常重要的意义. 相似文献
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The instrumentation and control (I&C) systems for the Lungmen nuclear power plant (LMNPP) are fully digitized based on microprocessor and software technology, and extensively utilize multiplexing networks. That is, undetectable software faults and common cause failures due to software errors may occur, and that will defeat the redundancy of a nuclear power plant (NPP). A diverse backup implementation for the digital I&C systems is an important means to defense against undetectable software faults.This paper presents system assessment of a quad-redundant reactor protection system (RPS) design for an Advanced Boiling Water Reactor (ABWR) by utilizing the field programmable gate array (FPGA) technology. The FPGA-based RPS has been assessed by using a full-scope engineering simulator for the LMNPP. Accident scenarios and abnormal conditions are inserted into the engineering simulator in order to activate the function of the FPGA-based RPS. In this study, conceptual design of the proposed quad-redundant FPGA-based RPS, including preliminary hardware architecture, software design and system assessment will be presented. The results demonstrate that the FPGA-based RPS system is a practical approach to implement a diverse backup for the digital I&C system of nuclear power plant applications.Also, the sensitivity study of probabilistic risk assessment (PRA) shows that RPS combined with ARI (Alternative Rod Insertion) contributes significant influence on the core damage frequency (CDF) calculation of LMNPP. The PRA sensitivity study is independent of the RPS technology. 相似文献
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Zhanguo Ma Hidekazu Yoshikawa Takashi Nakagawa 《Journal of Nuclear Science and Technology》2017,54(5):552-568
As part of the new risk monitor system, the software for the plant Defense-in-Depth (DiD) risk monitor system was designed based on the state-transition and finite-state machine, and then the knowledge-based software was developed by object-oriented method utilizing the Unified Modeling Language (UML). Currently, there are mainly two functions in the developed plant DiD risk monitor software that are knowledge-base editor which is used to model the system in a hierarchical manner and the interaction simulator that simulates the interactions between the different actors in the model. In this paper, a model for playing its behavior is called an Actor which is modeled at the top level. The passive safety AP1000 power plant was studied and the small-break loss-of-coolant accident (SBLOCA) design basis accident transient is modeled using the plant DiD risk monitor software. Furthermore, the simulation result is shown for the interactions between the actors which are defined in the plant DiD risk monitor system as PLANT actor, OPERATOR actor, and SUPERVISOR actor. This paper shows that it is feasible to model the nuclear power plant knowledge base using the software modeling technique. The software can make the large knowledge base for the nuclear power plant with small effort. 相似文献
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针对核电厂运行瞬态分析的功能需求,中国核动力研究设计院研发了PANTO(Program for Analysis of Normal Transient and Overpressure)软件。该软件基于成熟可靠的系统分析模型和特殊部件模型,采用模块化的软件设计理念,应用面向对象的C++语言和java语言,具有完全自主知识产权。PANTO软件通过了单元测试、集成测试和系统测试,基本消除了所有的代码缺陷。针对秦山二期核电厂阶跃负荷增大10%与额定功率下全部甩负荷瞬态试验进行了验证计算。结果表明,PANTO软件能够较好地模拟瞬态中关键参数的变化情况,计算精度满足工程应用要求,适用于压水堆核电厂运行瞬态分析。 相似文献