摘要
核级石墨是高温气冷堆重要的慢化剂、反射层和结构材料,其氧化腐蚀性能对反应堆安全运行至关重要,因此已成为核材料学科的研究热点之一。本文综述了国内外在核级石墨氧化腐蚀领域的研究现状,总结了核石墨氧化的化学动力学模型、失重率影响因子模型以及模拟计算模型,提出了高温气冷堆用石墨材料氧化腐蚀的研究方向。
Nuclear graphite serves as moderator, reflector and structural material in HTGRs. The oxidation performance of nuclear graphite is one of the most interested issues in nuclear material science. The present paper reviewed the oxidation kinetics, the models for influence factor of burn-off and the corrosion analysis model of nuclear graphite. Some new questions for further studying were given.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2012年第3期288-293,共6页
Atomic Energy Science and Technology
关键词
高温气冷堆
石墨
氧化腐蚀
high temperature gas-cooled reactor
graphite
oxidation
