HTTR(高温工学試験研究炉)の試験・運転と技術開発(2023年度)

Operation, test, research and development of the High Temperature Engineering Test Reactor (HTTR) (FY2023)

高温工学試験研究炉部

Department of HTTR

本報告書は、2023年度のHTTR(高温工学試験研究炉)の運転・保守管理状況、HTTRを用いた研究開発等についてまとめたものである。HTTRは熱出力30MW、原子炉出口冷却材温度950Cの我が国初の高温ガス炉の試験研究炉である。高温ガス炉は固有安全性に優れ、発電のみならず水素製造等の多様な産業利用が可能な原子炉として、将来の脱炭素社会に対応した次世代原子炉の候補として挙げられている。HTTRの目的は高温ガス炉技術の基盤の確立及び高温ガス炉の安全性の実証等であり、安全性実証試験、長期連続運転等の高温ガス炉の研究開発に関する各種実証試験並びに高温ガス炉の運転・保守に係る実績を有している。2023年度は、OECD/NEAの国際共同試験として、安全性実証試験(原子炉出力100%における炉心流量喪失試験)を実施し、高温ガス炉の高い安全性を実証した。

This report summarizes the activities carried out in the fiscal year 2023 about the operation and maintenance of the High Temperature Engineering Test Reactor (HTTR), the R&Ds using the HTTR, and so on. The HTTR is the first Japanese test reactor of High Temperature Gas-cooled Reactor (HTGR) type with 30 MW in thermal power and whose maximum outlet coolant temperature achieved 950 C. HTGRs are regarded as the promising candidates of the Next Generation Nuclear Plants conformed to the future decarbonized society because of the inherent safety characteristics as well as high temperature heat supply capability for not only power generation but for wide-ranging industrial uses such as hydrogen production, and so on. The purpose of the HTTR is establishment of basic HTGR technologies, demonstration of HTGR safety characteristics, and so on. The HTTR has had a lot of experience of HTGRs' operation and maintenance throughout rated power operations, safety demonstration tests, long-term high temperature operations and demonstration tests relevant to HTGRs' R&Ds. In the fiscal year 2023, the HTTR was confirmed its inherent safety of HTGR due to carry out the safety demonstration test (Loss of forced cooling test at the 100% power) as the international joint research of Organization for Economic Cooperation and Development/Nuclear Energy Agency (OECD/NEA).