高温ガス炉の保全技術の開発


英字タイトル:
Development of preservation technology for High Temperature Gas-cooled Reactor
著者:
古澤 孝之 本間 史隆 猪井 宏幸 澤畑 洋明 根本 隆弘 渡辺 周二 太田 幸丸
発刊日:
公開日:
カテゴリ: 第5回
キーワードタグ:

概要

Japan Atomic Energy Agency has constructed the HTTR (High Temperature engineering Test Reactor), which is the Japa n's first High Temperature Gas-cooled Reactor (HTGR). The HTTR achieved the full power of 30MW and reactor outlet coolant temperature of 950°C on April 19, 2004. Based on the HTTR maintenance experiences, the preservation techno logy for HTGR are developed. This paper describes its preservation philosophy and typical developed technologies.


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