NUCLEAR TECHNIQUES, Volume. 48, Issue 7, 070006(2025)

Research progress on environmental compatibility evaluation in liquid lead bismuth eutectic of stainless steels used in lead-cooled fast reactor

Jibo TAN1, Xinrui ZHANG1,2, Baoquan XUE1, Ziyu ZHANG1, and Xinqiang WU1、*
Author Affiliations
  • 1CAS Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
  • 2School of Materials Science and Engineering, Northeastern University, Shenyang 110819, China
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    The environmental compatibility issue of structural materials in liquid lead bismuth eutectic (LBE) is a bottleneck problem restricting the development and construction of lead-cold fast reactors. 9~12Cr ferritic/martensitic and austenitic stainless steels are the preferred key equipment structural materials for lead-cold fast reactors, but facing severe liquid metal corrosion (oxidation and dissolution) problems in high-temperature liquid LBE environments. Usually, an appropriate amount of Si or Al is added to the alloy to enhance its resistance to liquid metal corrosion. This paper reviews the research progress on the oxidation, dissolution, slow strain rate tensile, creep, fatigue and crack propagation behavior of 9~12Cr ferritic/martensitic steels, austenitic stainless steels, Si-enhanced ferritic/martensitic steels and austenitic stainless steels, and Al forming austenitic stainless steels in the liquid LBE environment. The liquid metal embrittlement sensitivity and damage mechanism of ferritic/martensitic steels (body-centered cubic) and austenitic stainless steels (face-centered cubic) in liquid LBE environment are investigated. The existing problems in the current research are summarized, and the future research directions development visions are prospected.

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    Jibo TAN, Xinrui ZHANG, Baoquan XUE, Ziyu ZHANG, Xinqiang WU. Research progress on environmental compatibility evaluation in liquid lead bismuth eutectic of stainless steels used in lead-cooled fast reactor[J]. NUCLEAR TECHNIQUES, 2025, 48(7): 070006

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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: Apr. 19, 2025

    Accepted: --

    Published Online: Sep. 15, 2025

    The Author Email: Xinqiang WU (WUXinqiang)

    DOI:10.11889/j.0253-3219.2025.hjs.48.250172

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