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Thermal hydraulics of sodium-cooled fast reactors; Key design and safety issues and highlights

ナトリウム冷却高速炉の熱流動現象; 設計と安全に関する重要な項目と特記事項

二ノ方 壽*; 上出 英樹 

Ninokata, Hisashi*; Kamide, Hideki

日本の高速炉開発に関して、特に機構が進めるJSFRの設計研究と関連する熱流動研究に焦点を当てて熱流動観点で重要なpointを述べる。JSFRでは幾つかの革新技術、例えば完全自然循環方式崩壊熱除去系,炉心損傷事故時の再臨界を排除できる炉心概念が、より高い安全レベルを達成するために考案,研究され、その評価が進んでいる。ここではその研究開発成果を紹介する。

In this paper key issues and highlighted topics in thermal hydraulics are discussed in the current Japan's sodium-cooled fast reactor development efforts. In particular, design study and related researches of the Japan Sodium-cooled Fast Reactor (JSFR) are focused. Several innovative technologies, e.g., fully natural circulation decay heat removal and recriticality-free core, have been investigated in order to reduce construction cost and to achieve higher level of reactor safety. Preliminary evaluations of innovative technologies to be applied to JSFR are on-going. Here, progress of design study is introduced. Then, research and development activities are briefly reviewed.

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パーセンタイル:18.71

分野:Nuclear Science & Technology

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