Ming Jiao , Li Zhang , Ping Cheng , Mingguang Zheng , Xiaoqiang Liu
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引用次数: 0
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.
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.