Research Progress on Liquid Metal Embrittlement Behavior of Candidate Structural Materials for Lead-Bismuth Reactors

As one of the fourth-generation nuclear reactors, the Lead-cooled Fast Reactor (LFR) has garnered significant attention owing to the superior thermophysical and neutron properties of the Lead-Bismuth Eutectic (LBE). However, the compatibility between its structural materials and liquid LBE remains a...

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Main Author: Ma Guobao, Tang Zhengxin, Bao Hansheng, He Xikou
Format: Article
Language:zho
Published: Editorial Office of Special Steel 2025-08-01
Series:Teshugang
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Online Access:https://www.specialsteeljournal.com/fileup/1003-8620/PDF/2025-00119.pdf
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author Ma Guobao, Tang Zhengxin, Bao Hansheng, He Xikou
author_facet Ma Guobao, Tang Zhengxin, Bao Hansheng, He Xikou
author_sort Ma Guobao, Tang Zhengxin, Bao Hansheng, He Xikou
collection DOAJ
description As one of the fourth-generation nuclear reactors, the Lead-cooled Fast Reactor (LFR) has garnered significant attention owing to the superior thermophysical and neutron properties of the Lead-Bismuth Eutectic (LBE). However, the compatibility between its structural materials and liquid LBE remains a critical barrier to its advancement. Liquid Metal Embrittlement (LME), one of the most prominent challenges, markedly diminishes the elongation and fatigue life of structural materials under specific conditions, thereby jeopardizing the safety and reliability of the reactors. This paper focuses on the LME issue in LFR structural materials, elucidating the LME behavior of key candidate structural materials-ferritic/martensitic steel, aluminum-containing ferritic steel, austenitic steel, and aluminum-containing austenitic steel in high-temperature liquid LBE, while clarifying their respective sensitivities to LME of various materials To address this formidable challenge of LME, the paper examines various influencing factors, including temperature, oxygen concentration, strain rate, pre-exposure, and metallurgical state, summarizing the current understanding of how these factors affect LME and their underlying mechanisms. Finally, based on existing research findings, the paper provides an outlook on the future prospects for enhancing the comprehension of the LME mechanism.
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institution Kabale University
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publisher Editorial Office of Special Steel
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spelling doaj-art-79e1288cda3c4d9a8e7171a12bd7e23e2025-08-20T03:43:55ZzhoEditorial Office of Special SteelTeshugang1003-86202025-08-01464243410.20057/j.1003-8620.2025-00119Research Progress on Liquid Metal Embrittlement Behavior of Candidate Structural Materials for Lead-Bismuth ReactorsMa Guobao, Tang Zhengxin, Bao Hansheng, He Xikou01 Collaborative Innovation Center of Steel Technology, University of Science and Technology Beijing, Beijing 100083, China;2 Institute for Special Steels, Central Iron and Steel Research Institute Co., Ltd. (CISRI), Beijing 100081, ChinaAs one of the fourth-generation nuclear reactors, the Lead-cooled Fast Reactor (LFR) has garnered significant attention owing to the superior thermophysical and neutron properties of the Lead-Bismuth Eutectic (LBE). However, the compatibility between its structural materials and liquid LBE remains a critical barrier to its advancement. Liquid Metal Embrittlement (LME), one of the most prominent challenges, markedly diminishes the elongation and fatigue life of structural materials under specific conditions, thereby jeopardizing the safety and reliability of the reactors. This paper focuses on the LME issue in LFR structural materials, elucidating the LME behavior of key candidate structural materials-ferritic/martensitic steel, aluminum-containing ferritic steel, austenitic steel, and aluminum-containing austenitic steel in high-temperature liquid LBE, while clarifying their respective sensitivities to LME of various materials To address this formidable challenge of LME, the paper examines various influencing factors, including temperature, oxygen concentration, strain rate, pre-exposure, and metallurgical state, summarizing the current understanding of how these factors affect LME and their underlying mechanisms. Finally, based on existing research findings, the paper provides an outlook on the future prospects for enhancing the comprehension of the LME mechanism.https://www.specialsteeljournal.com/fileup/1003-8620/PDF/2025-00119.pdflead-cooled fast reactor; lead-bismuth eutectic; liquid metal embrittlement; structural materials; influencing factors
spellingShingle Ma Guobao, Tang Zhengxin, Bao Hansheng, He Xikou
Research Progress on Liquid Metal Embrittlement Behavior of Candidate Structural Materials for Lead-Bismuth Reactors
Teshugang
lead-cooled fast reactor; lead-bismuth eutectic; liquid metal embrittlement; structural materials; influencing factors
title Research Progress on Liquid Metal Embrittlement Behavior of Candidate Structural Materials for Lead-Bismuth Reactors
title_full Research Progress on Liquid Metal Embrittlement Behavior of Candidate Structural Materials for Lead-Bismuth Reactors
title_fullStr Research Progress on Liquid Metal Embrittlement Behavior of Candidate Structural Materials for Lead-Bismuth Reactors
title_full_unstemmed Research Progress on Liquid Metal Embrittlement Behavior of Candidate Structural Materials for Lead-Bismuth Reactors
title_short Research Progress on Liquid Metal Embrittlement Behavior of Candidate Structural Materials for Lead-Bismuth Reactors
title_sort research progress on liquid metal embrittlement behavior of candidate structural materials for lead bismuth reactors
topic lead-cooled fast reactor; lead-bismuth eutectic; liquid metal embrittlement; structural materials; influencing factors
url https://www.specialsteeljournal.com/fileup/1003-8620/PDF/2025-00119.pdf
work_keys_str_mv AT maguobaotangzhengxinbaohanshenghexikou researchprogressonliquidmetalembrittlementbehaviorofcandidatestructuralmaterialsforleadbismuthreactors