核工程
冷却液
材料科学
碳化硅
核反应堆
核能
环境科学
废物管理
核物理学
机械工程
工程类
冶金
物理
作者
Jin Iwatsuki,Kazuhiko Kunitomi,Hideaki Mineo,Tetsuo Nishihara,Nariaki Sakaba,Masayuki Shinozaki,Yukio Tachibana,Xing L. Yan
出处
期刊:Elsevier eBooks
[Elsevier]
日期:2021-01-01
卷期号:: 1-16
被引量:10
标识
DOI:10.1016/b978-0-12-821031-4.00001-4
摘要
A high temperature gas-cooled reactor (HTGR) is a nuclear reactor that can supply high temperature heat energy of 750°C–950°C by using a spherical fuel coated with ceramics such as carbon and silicon carbide, inert helium gas as a coolant, and graphite as a moderator. At present, a light water reactor is mainly used for nuclear power generation, but HTGR is attracting attention mainly for the following two reasons: the first reason is that the nuclear heat should be used for fields other than power generation, because fossil fuels and renewable energy have a limit to meet the increasing energy demand in the future. The second reason is excellent safety. Among all reactor types, HTGR has excellent inherent safety and its safety has been demonstrated in experimental reactors. This chapter explained the features of HTGR such as structure, heat application, and the history of development.
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