A new cross-scale model for leakage-rate prediction of metal-to-metal seals under high-pressure conditions

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-05-01 Epub Date: 2025-03-06 DOI:10.1016/j.nucengdes.2025.113981
Weixi Zhang , Jinhui Wang , Xiaoming Huang , Guoliang Xu , Du Zhou
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Abstract

In order to better reveal the leakage mechanism of metal-to-metal valves under high-pressure condition in nuclear power plants, a cross-scale prediction method is proposed, which integrates various simulation techniques such as mesoscopic flow, mesoscopic contact, and macroscopic contact. On this basis, the flow resistance network analysis method is introduced to better evaluate the influence of high-pressure liquid penetration on the leakage characteristics of metal-to-metal valves. In this manner, the model can quantitatively evaluate the impact of various parameters on the leakage rate, such as surface morphology, geometric structure, sealing load, and fluid pressure. A leakage-rate test device of multi parameter metal-to-metal seals is designed and constructed. The effectiveness of the theoretical prediction method is verified based on the experimental results. Subsequent simulation studies have revealed that as the medium pressure increases or the sealing force decreases, the distribution of contact stress on the sealing surface exhibits three distinct patterns: unpenetrated, near-penetrated, and penetrated. The leakage rate is highly sensitive to changes of sealing force in the penetrated pattern, while the leakage rate is highly affected by surface morphology in the unpenetrated pattern. Curves of required contact stresses and fluid pressures were calculated and compared for different contact widths, using the maximum allowable leakage rate (Qlim = 1.2 g/min) as an indicator. An abnormal increase in the slope of the curves (from 0.27 to 4.95) was found for high pressures (Pfluid > 5 MPa), high roughness (0.3 μm) and small contact widths (4 mm), suggesting that the sealing performance is dominated by a combination of micro-flow and macro-contact. Reverse penetration can greatly reduce the sensitivity of leakage rate to sealing force. The research in the article will permit improved design techniques that significantly improve the sealing performance of metal-to-metal seals.

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高压条件下金属对金属密封泄漏率预测的跨尺度新模型
为了更好地揭示核电站高压工况下金属对金属阀门泄漏机理,提出了一种融合介观流动、介观接触、宏观接触等多种模拟技术的跨尺度预测方法。在此基础上,引入流动阻力网络分析方法,更好地评价高压液体渗透对金属对金属阀门泄漏特性的影响。这样,该模型可以定量评价各种参数对泄漏率的影响,如表面形貌、几何结构、密封载荷、流体压力等。设计并制造了一种多参数金属对金属密封泄漏率试验装置。实验结果验证了理论预测方法的有效性。随后的模拟研究表明,随着介质压力的增加或密封力的减小,密封面上的接触应力分布呈现出三种不同的模式:未渗透、近渗透和渗透。泄漏率在渗透模式下对密封力的变化高度敏感,而在未渗透模式下,泄漏率受表面形貌的影响很大。以最大允许泄漏率(Qlim = 1.2 g/min)为指标,计算并比较了不同接触宽度下所需的接触应力和流体压力曲线。高压(Pfluid >;5 MPa)、高粗糙度(0.3 μm)和小接触宽度(4 mm),表明微流动和宏观接触共同主导了密封性能。反渗透可以大大降低泄漏率对密封力的敏感性。本文中的研究将允许改进设计技术,显着提高金属对金属密封的密封性能。
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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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