Characterization of long-term evolution of leakage rates of O-ring seals in nuclear power plant under high-temperature and high-pressure conditions

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Ming Li , Lei He , Dengke Zheng , Xing Fang , Xiaoming Huang , Guoliang Xu
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Abstract

Under accident conditions, the sustained high temperature and high pressure (HTHP) environment within the containment structure poses a threat to the penetration seals. This study integrates finite element analysis of the mechanical properties of O-ring, both hyperelastic and viscoelastic characteristics, and an interfacial leakage model to predict the variation in O-ring leakage rates over time in HTHP environments. A series of leakage test experiments are conducted to validate the predictive model, indicating good agreement between experimental and predicted values. The effects of HTHP on non-aged O-rings (short-term service) are analyzed through mechanical simulations and leakage rate calculations. The results reveal that high temperatures positively and reversibly affect the O-ring seals, with hazardous conditions mainly resulting from over-pressurization. However, during the long-term service of aged O-rings, thermal aging caused by high temperatures significantly influences leakage rates. The thermal aging coupled with high pressure can cause material damage (such as rubber being squeezed out) and functional failures (excessive leakage rates). The long-term leakage rates of O-rings at high temperatures in further investigation exhibits a time–temperature equivalence. The master curve is plotted to derive an equation that describes the relationship between leakage rates, temperature, and time under specific pressure conditions. The equation indicates that the dimensionless leakage rate serves as an indicator of seal degradation and enables the quantitative evaluation of the long-term service life of the O-rings using the maximum allowable leakage rate. These findings are applicable within the range of accidental operating conditions for containment structures, including temperatures up to 160 °C and pressures up to 0.75 MPa.
高温高压条件下核电站 O 型圈密封件泄漏率的长期演变特征
在事故条件下,安全壳结构内的持续高温高压(HTHP)环境对贯穿密封件构成威胁。本研究整合了 O 形环机械性能的有限元分析(包括超弹性和粘弹性特性)和界面泄漏模型,以预测 HTHP 环境中 O 形环泄漏率随时间的变化。为验证预测模型,进行了一系列泄漏测试实验,结果表明实验值与预测值之间具有良好的一致性。通过机械模拟和泄漏率计算,分析了 HTHP 对非老化 O 形环(短期使用)的影响。结果表明,高温会对 O 形圈密封件产生正向和可逆的影响,危险情况主要来自于过压。然而,在老化 O 形环的长期使用过程中,高温引起的热老化会对泄漏率产生重大影响。热老化加上高压会导致材料损坏(如橡胶被挤出)和功能失效(泄漏率过高)。在进一步调查中,O 形圈在高温下的长期泄漏率呈现出时间-温度等效关系。绘制主曲线可以得出一个方程,描述特定压力条件下泄漏率、温度和时间之间的关系。方程式表明,无量纲泄漏率可作为密封退化的指标,并能利用最大允许泄漏率对 O 形圈的长期使用寿命进行定量评估。这些发现适用于安全壳结构的意外运行条件范围,包括温度高达 160 °C 和压力高达 0.75 MPa。
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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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