Research and development activities of JAEA for HTGR system realization

Mineo, Hideaki  ; Nishihara, Tetsuo ; Ohashi, Hirofumi ; Goto, Minoru  ; Sato, Hiroyuki  ; Takegami, Hiroaki 

High-Temperature Gas-cooled Reactor (HTGR) is one of thermal neutron reactor-type that employs helium gas coolant and graphite moderator. It has excellent inherent safety and can supply high-temperature heat which can be used not only for electric power generation but also for a wide range of application such as hydrogen production. Therefore, HTGR is expected to be an effective technology for reducing greenhouse gases in Japan as well as overseas. In this paper, we will introduce the forefront of technological development that JAEA is working toward the realization of an HTGR system consisting of a high temperature gas reactor and heat utilization facilities such as gas-turbine power generation and hydrogen production.