摘要
本文通过对石墨在高温气冷堆中的运行环境进行了分析,研究了在石墨堆内构件设计中的关键问题和在高温气冷堆单个模块及其未来发展中核级石墨的需求。从原料、成型及中子辐照等角度分析了核级石墨国产化研究方向。根据核级石墨目前的研发形势,进行了风险问题分析。
The paper studies the key problems in the design of reactor graphite internals through analyzing the work environment of graphite in high temperature gas-cooled reactor. It is researched that the requirement of nuclear graphite for one high temperature gas-cooled reactor and its development. The study orientation made in china is analyzed from raw materials,molding and neutron irradiation,etc. The risk problems are analyzed based on the current development instance.
出处
《核安全》
2014年第4期34-38,共5页
Nuclear Safety
基金
大型先进压水堆及高温气冷堆核电站重大专项
项目编号2008ZX06905-002
关键词
高温气冷堆
核级石墨
设计
风险
high temperature gas-cooled reactor
nuclear graphite
design
risk
