Research progress on thermal aging of reactor pressure vessel steel

被引:1
|
作者
Gao, Junkang [1 ]
Li, Jun [1 ]
Li, Junwan [2 ]
Li, Shaohong [1 ]
Li, Zhimin [3 ]
机构
[1] Kunming Univ Sci & Technol, Fac Mat Sci & Engn, Kunming 650093, Peoples R China
[2] Shanghai Univ, Sch Mat & Engn, Shanghai, Peoples R China
[3] Yunnan Coll Business Management, Kunming 650106, Peoples R China
关键词
thermal aging; SA508Gr.3; steel; RPV; Cr-Mo-V steel; embrittlement mechanism; GRAIN-BOUNDARY SEGREGATION; NEUTRON-IRRADIATED FE; STRENGTH BAINITIC STEELS; VVER-1000 RPV STEELS; LOW-ALLOY STEELS; CR-MO-V; MECHANICAL-PROPERTIES; ATOM-PROBE; MICROSTRUCTURAL EVOLUTION; PHOSPHORUS SEGREGATION;
D O I
10.1177/02670836241259859
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Nuclear energy is highly valued in many countries for its reliability, cleanliness and cost-effectiveness. Ensuring the safe development and utilization of nuclear energy has become crucial for addressing the global energy shortage and mitigating climate change. The reactor pressure vessel (RPV) is exposed to a high-temperature, high-corrosion and high-radiation environment, the RPV materials have a significant impact on the stability and safety of a nuclear power station. In this paper, the effects of long-term high-temperature hot aging on microstructure and mechanical properties of RPV steel, as well as the research progress in embrittlement mechanism and service life prediction, are reviewed. At the same time, the existing problems and further research directions of RPV steel are pointed out.
引用
收藏
页数:29
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