主催: 一般社団法人 日本機械学会
会議名: 第27回 動力・エネルギー技術シンポジウム
開催日: 2023/09/20 - 2023/09/21
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. HTGR can be used in various ways such as hydrogen production and process heat supply as well as power generation. 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 volume 5 provides the latest research on HTGR development and utilization, beginning with an analysis of the history of HTGRs.
