泄漏率预测模型研究及其在双偏置蝶阀多工况转换中的应用

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Jiangfan Xiong , Yubing Bu , Guojun Zhang , Jian Liu , Guoliang Xu , Xiaoming Huang
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引用次数: 0

摘要

大量阀门是核电站安全壳压力边界的重要组成部分,必须严格控制其在事故条件下的泄漏率。本研究提出了一种构建阀门泄漏率预测模型的方法,以研究事故工况下的阀门泄漏特性。以双偏置蝶阀(DOBV)为研究对象,通过对密封的微观和宏观接触力学进行有限元分析(FEA),结合现有的界面泄漏模型,建立了多参数泄漏率预测模型。该模型能够预测不同参数的影响,包括温度、压力和湿度。然后将其与多工况泄漏测试的实验值进行比较,对其进行验证。基于该模型,对工作条件参数对阀门泄漏率的影响进行了数值研究,并提出了无量纲泄漏率关系:Qr=EPETEm,其中 EP、ET 和 Em 分别为压力、温度和湿度换算系数。这些系数与各自的无量纲状态参数呈幂函数关系。进一步分析表明,这些关系的幂函数与粗糙度无关,与密封材料和密封结构的相关性较弱。应用转换方程比较分析了该阀门在两种假定事故情况下的泄漏模式,并得出了一些与动态泄漏率控制有关的有用结论。本文介绍的方法主要针对接触密封泄漏机理,并可扩展到其他安全壳贯穿件。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Study on a leakage rate predictive model with Application in Multi-Conditions conversion for Double-Offset butterfly valves
A significant number of valves constitute a vital component of the containment pressure boundary of a nuclear power plant, and their leakage rates under accident conditions must be tightly controlled. In this study, a methodology for the construction of a predictive model of valve leakage rate is put forth the study of valve leakage characteristics under accident conditions. Taking the double-offset butterfly valves (DOBV) as the research object, its multi-parameter leakage rate predictive model is developed through finite element analysis (FEA) of the microscopic and macroscopic contact mechanics of the sealing, that are then combined with an existing interfacial leakage model. This model is able to predict the effects of different parameters, including the temperature, pressure, and humidity. It is then verified by comparing it with the experimental values of the multi-operating conditions leakage test. Based on this model, the impact of operating condition parameters on the leakage rate of the valve is numerically studied and a dimensionless leakage rate relationship is proposed: Qr=EPETEm, where EP,ET,and Em are pressure, temperature, and humidity conversion factors, respectively. These factors are in a power function relationship with their respective dimensionless state parameters. Further analysis demonstrates that the powers of these relationships are independent of roughness and weakly correlated with seal material and seal structure. The leakage pattern of this valve under two hypothetical accident scenarios is comparatively analyzed by applying the conversion equation, and some useful conclusions related to dynamic leakage rate control are drawn. The methodology presented in this paper is central to the contact seal leakage mechanism and can be extended to other containment penetrations.
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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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