包层(金属加工)
核工程
材料科学
核裂变
核反应堆
奥氏体不锈钢
结构材料
裂变
腐蚀
中子
冶金
工程类
核物理学
物理
作者
Guan Wang,Zhaohao Wang,Di Yun
出处
期刊:Metals
[Multidisciplinary Digital Publishing Institute]
日期:2023-08-28
卷期号:13 (9): 1524-1524
被引量:15
摘要
Lead-cooled fast reactors (LFRs) are considered one of the most promising technologies to meet the requirements introduced for advanced nuclear systems. LFRs have higher neutron doses, higher temperatures, higher burnup and an extremely corrosive environment. The failure studies of claddings play a vital role in improving the safety criteria of nuclear reactors and promoting research on advanced nuclear materials. This paper presented a comprehensive review of the extreme environment in LFRs based on the fuel performance analyses and transient analyses of reference LFRs. It provided a clear image of cladding failure, focusing on the underlying mechanisms, such as creep, rupture, fatigue, swelling, corrosion, etc., which are resulted from the motions of defects, the development of microcracks and accumulation of fission products to some extent. Some fundamental parameters and behavior models of Ferritic/Martensitic (F/M) steels and Austenitic stainless (AuS) steels were summarized in this paper. A guideline for cladding failure modelling was also provided to bridge the gap between fundamental material research and realistic demands for the application of LFRs.
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