核电站气动控制阀可靠性评估与维修计划

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Guru Prakash , Mahesh D. Pandey
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引用次数: 0

摘要

在核电站中,气动阀(aov)用于控制和隔离不同的过程系统。气动执行器和阀门的其他控制部件的退化会对AOV的性能产生不利影响。因此,阀门大修(OH)以固定的间隔进行,主要基于供应商的建议和工厂人员的经验。本文提出了一种评估阀门可靠性的概率方法,并以此作为维修计划的依据。本文提出了一种贝叶斯方法来建立阀门寿命分布模型,并根据工厂提供的在役数据更新其参数。使用该模型,确定阀门OH间隔以在该间隔内达到目标可靠性水平。本文提出了一个实际的案例研究,该研究利用了连接到加拿大核电站蒸汽发生器的32级控制阀的维修数据。所提出的方法表明,在役阀门令人满意的功能为延长其OH间隔提供了有价值的信息。因此,所提出的方法可以显著提高阀门维护程序的效率。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Reliability assessment and maintenance planning of air-operated control valves used in a nuclear power plant
Air-operated valves (AOVs) are used to control and isolate different process systems in a nuclear power plant. The performance of an AOV is adversely affected by degradation in the pneumatic actuator and other control components of the valve. Therefore, valve overhauls (OH) are performed at a fixed interval that is mainly based on the vendor’s recommendations and the experience of the plant personnel. This paper presents a probabilistic approach to assess valve reliability and uses it as a basis to plan maintenance. The paper presents a Bayesian approach to model the valve lifetime distribution and update its parameters based on the in-service data available from the plant. Using this model, the valve OH interval is determined to achieve a target reliability level over the interval. A practical case study is presented that utilizes maintenance data from a fleet of 32-level control valves connected to steam generators at a Canadian nuclear power station. The proposed approach demonstrates that the satisfactory functioning of an in-service valve provides valuable information for extending its OH interval. Thus, the proposed approach can significantly improve the efficiency of the valve maintenance program.
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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