Cladding Failure Modelling for Lead-Based Fast Reactors: A Review and Prospects

被引:3
|
作者
Wang, Guan [1 ]
Wang, Zhaohao [2 ]
Yun, Di [2 ,3 ]
机构
[1] Lanzhou Univ, Sch Nucl Sci & Technol, Lanzhou 730000, Peoples R China
[2] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian 710049, Peoples R China
[3] Xi An Jiao Tong Univ, State Key Lab Multiphase Flow, Xian 710049, Peoples R China
关键词
cladding failure; lead-cooled fast reactors; extreme environment; failure mechanisms; DISPERSION-STRENGTHENED STEELS; BISMUTH EUTECTIC LBE; LONG-TERM BEHAVIORS; FUEL PERFORMANCE; MATERIALS CHALLENGES; STRUCTURAL-MATERIALS; MARTENSITIC STEELS; NUCLEAR-POWER; ANALYSIS CODE; OXIDE LAYER;
D O I
10.3390/met13091524
中图分类号
T [工业技术];
学科分类号
08 ;
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.
引用
收藏
页数:24
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