反应堆压力容器
脆化
材料科学
核工程
核能
压力容器
可靠性(半导体)
经济短缺
核反应堆
使用寿命
核电站
微观结构
冶金
法律工程学
功率(物理)
工程类
复合材料
核物理学
物理
语言学
哲学
量子力学
政府(语言学)
作者
Junkang Gao,Jun Li,Junwan Li,Shaohong Li,Zhimin Li
标识
DOI:10.1177/02670836241259859
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.
科研通智能强力驱动
Strongly Powered by AbleSci AI