動力・エネルギー技術の最前線講演論文集 : シンポジウム
Online ISSN : 2424-2950
セッションID: A232
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「部門設立30周年記念出版Vol.4高温ガス炉」
(2)我が国の高温ガス炉技術に基づく高温ガス炉実証炉開発
*橘 幸男野口 弘喜角田 淳弥大橋 弘史佐藤 博之坂場 成昭
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For the High-Temperature Gas-cooled Reactor (HTGR) demonstration reactor, establishment of an annular core, enlargement of isolation valves, etc., establishment of codes and standards, establishment of technology to connect the hydrogen production system to the HTGR, etc. are required. In FY2022, JAEA started a project to connect hydrogen production system to the HTTR. JAEA will advance safety evaluations to ensure sufficient safety, and confirm the hydrogen production technology using nuclear heat for the first time in the world. JAEA has been requested by the UK and Poland for technical cooperation for the introduction of HTGRs, and has started technical cooperation to make the best use of the technology for the future demonstration reactor in Japan. This report introduces the current status of development for the HTGR demonstration reactor.

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