NUCLEAR TECHNIQUES, Volume. 48, Issue 7, 070008(2025)

Research progress of oxidation and corrosion of iron base alloy by high temperature alkali metals

Borui CHEN1,2, Yugao MA3, Zaiyong MA1,2、*, Liangming PAN1,2, Simiao TANG1,2, Longxiang ZHU1,2, and Qiang LIAN1,2
Author Affiliations
  • 1Key Laboratory of Low-grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, Chongqing 400044, China
  • 2Department of Nuclear Engineering and Technology, Chongqing University, Chongqing 400044, China
  • 3Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China
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    Alkali metals have high thermal conductivity and low melting points, making them widely used in nuclear industry and aerospace technology. In high-temperature alkali metals systems, iron-based alloys are widely used as the material of the heating wall. Due to the highly active physicochemical properties of alkali metals, oxidation and corrosion to iron-based alloys would take place under prolonged high-temperature conditions, which alters the microstructure, surface composition, and morphological characteristics of the materials, hence has influences on their mechanical and chemical properties. In this paper, the experimental methods of the oxidation and corrosion in high-temperature alkali metals system are firstly summarized, along with the oxidation and corrosion depth models and the solid metal mass loss models. The elements transport in liquid metal and solid metal during the oxidation and corrosion process are discussed. Subsequently, some methods of protection against the oxidation and corrosion are presented, such as adding buffer and surface coating. Finally, current research status and future development trend were presented.

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    Borui CHEN, Yugao MA, Zaiyong MA, Liangming PAN, Simiao TANG, Longxiang ZHU, Qiang LIAN. Research progress of oxidation and corrosion of iron base alloy by high temperature alkali metals[J]. NUCLEAR TECHNIQUES, 2025, 48(7): 070008

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    Paper Information

    Category: Special Issue on The First Academic Annual Conference of the Research Reactor and Innovative Reactor Association of Chinese Nuclear Society and Advanced Nuclear Power System Reactor Engineering

    Received: Dec. 13, 2024

    Accepted: --

    Published Online: Sep. 15, 2025

    The Author Email: Zaiyong MA (MAZaiyong)

    DOI:10.11889/j.0253-3219.2025.hjs.48.240513

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