Research on the corrosion resistance of porous coatings for heat transfer enhancement on the head of nuclear reactor pressure vessels

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2024-12-01 Epub Date: 2024-09-20 DOI:10.1016/j.nucengdes.2024.113597
Ming Jiao , Li Zhang , Ping Cheng , Mingguang Zheng , Xiaoqiang Liu
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Abstract

The preparation of a porous coating on the outer surface of nuclear power reactor pressure vessel’s lower head is considered an effective measure to enhance heat transfer and ensure safety under the condition of In-Vessel Retention (IVR) during severe accidents. However, oxidation and corrosion of the porous coating are inevitable, as it will be exposed to the marine atmosphere during the vessel’s construction and operation phases. Therefore, it is necessary to strengthen its corrosion resistance under the premise of high critical heat flux (CHF). In this paper, based on the successful development of high CHF porous coatings, a composite coating consisting of a Ni-Cr bottom layer and a 316L stainless steel porous coating was designed and prepared by flame spraying on SA-508 Gr.3 steel. The corrosion resistance of the composite coating was evaluated by Neutral Salt Spray Test (NSS) and the corrosion mechanism of the coating was analyzed. The results showed that the Ni-Cr bottom coating exhibited no obvious corrosion after 240 h of the NSS test, but the corrosion resistance of the porous coating was decreased due to surface oxidation, chromium deficiency in the particle melting zone and the presence of ferrite. By incorporating corrosion-resistant alloying elements into 316L powders, the corrosion resistance of the coating can be significantly improved while preserving its porosity. The investigation of porous composite coatings for reactor pressure vessels is a critical endeavor with the potential to significantly enhance the performance, safety, and longevity of nuclear reactors.

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用于增强核反应堆压力容器头部传热的多孔涂层的耐腐蚀性研究
在核电反应堆压力容器下封头外表面制备多孔涂层被认为是一种有效措施,可在严重事故发生时增强传热并确保舱内滞留(IVR)条件下的安全。然而,由于多孔涂层在建造和运行阶段会暴露在海洋大气中,其氧化和腐蚀不可避免。因此,有必要在高临界热通量(CHF)的前提下增强其耐腐蚀性。本文在成功开发高临界热通量多孔涂层的基础上,设计了一种由镍铬底层和 316L 不锈钢多孔涂层组成的复合涂层,并通过火焰喷涂在 SA-508 Gr.3 钢上制备而成。通过中性盐雾试验(NSS)评估了复合涂层的耐腐蚀性,并分析了涂层的腐蚀机理。结果表明,Ni-Cr 底涂层在 NSS 试验 240 小时后未出现明显腐蚀,但由于表面氧化、颗粒熔化区缺铬和铁素体的存在,多孔涂层的耐腐蚀性降低。通过在 316L 粉末中加入耐腐蚀合金元素,可以在保持多孔性的同时显著提高涂层的耐腐蚀性。反应堆压力容器多孔复合涂层的研究是一项至关重要的工作,有可能显著提高核反应堆的性能、安全性和寿命。
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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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