高温气冷堆用核石墨高温水蒸气腐蚀研究进展  

Research progress on high temperature water vapor corrosion of nuclear graphite for high temperature gas-cooled reactors

作　　者：段高晗 郝少昌[1] 叶丽古玛 Duan Gao-han;Hao Shao-chang;Yeli Guma(Institute of Nuclear and New Energy Technology,Tsinghua University,Beijing 100084,China)

机构地区：[1]清华大学核能与新能源技术研究院,北京100084

出　　处：《炭素技术》2024年第5期6-16,共11页Carbon Techniques

摘　　要：核石墨是高温气冷堆燃料元件的基体材料和堆芯主要结构材料,其高温水蒸气腐蚀性能对反应堆在进水事故工况下的整体安全至关重要,因此核石墨腐蚀行为研究是高温气冷堆关键材料研究的重点。本文综述了国内外的相关研究,总结了高温气冷堆正常运行及事故工况、石墨水蒸气腐蚀的反应机理研究、石墨腐蚀后的微观表征研究及计算模拟在石墨水蒸气腐蚀中的应用,指出未来高温气冷堆用核石墨腐蚀的研究中还需要解决的问题。Nuclear graphite is the matrix material of fuel elements and the structural material of the core in high temperature gas-cooled reactors.The high temperature water vapor corrosion performance of the nclear traphite is crucial for the overall safety of the reactor under water ingress accident conditions.Therefore,the study of the corrosion behavior of nuclear graphite is a key material research focus in high temperature gas-cooled reactors.This article reviews relevant research at home and abroad,summarizes the normal operation and accident conditions of high temperature gas-cooled reactors,the reaction mechanism of graphite steam corrosion,the microscopic characterization of graphite corrosion,and the application of computational simulation in graphite steam corrosion.It points out the problems that need to be solved in future research on graphite corrosion.

关 键 词：石墨 高温气冷堆 水蒸气腐蚀 

分 类 号：TL35[核科学技术—核技术及应用]