Issues and future direction of thermal-hydraulics research and development in nuclear power reactors

原子炉熱流動研究の課題と今後の方向性

Saha, P.*; Aksan, N.*; Andersen, J.*; Yan, J.*; Simoneau, J. P.*; Leung, L.*; Bertrand, F.*; 青砥 紀身 ; 上出 英樹 

Saha, P.*; Aksan, N.*; Andersen, J.*; Yan, J.*; Simoneau, J. P.*; Leung, L.*; Bertrand, F.*; Aoto, Kazumi; Kamide, Hideki

本論文は、2011年9月のNURETH-14会議でのパネル発表(原子炉熱流動研究の課題と今後の方向性)をまとめたものである。熱流動研究の進展は運転されている炉の性能向上に貢献するとともに、開発中,第4世代炉の実験,解析の分野でさらなる研究開発が進められている。計算機能力の向上に伴い、微細スケール,複合現象の解析モデルをシステムコードと組合せ、課題解決が図られている。

The paper archives the proceedings of an expert panel discussion on the issues and future direction of thermal-hydraulic research and development in nuclear power reactors held at the NURETH-14 conference in September 2011. Advances in thermal hydraulics have significantly improved the performance of operating reactors and are continuing in both experimental and computational areas for reactors under construction or ready for near-term deployment, and advanced Generation-IV reactors. As the computing power increases, the fine-scale multi-physics computational models, coupled with the systems analysis code, are expected to provide answers to many challenging problems in both operating and advanced reactor designs.