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Thermal-hydraulic research in JAEA; Issues and future directions

Akimoto, Hajime; Ohshima, Hiroyuki; Kamide, Hideki ; Nakagawa, Shigeaki  ; Ezato, Koichiro; Takase, Kazuyuki; Nakamura, Hideo  

Thermal-hydraulics researches at JAEA are performed in many nuclear R&D areas that investigate fusion reactor, fast reactors (FR), high temperature gas cooled reactors (HTGR), and light water reactors (LWRs). These researches are composed of both experimental and analytical efforts. Experimental efforts cover from small-scale fundamental works to large-scale system-integrated tests. Analytical efforts cover both so-called one-dimensional system analysis codes and detailed three-dimensional CFD codes. The thermal-hydraulic phenomena dealt at JAEA cover both normal operation conditions and accident conditions including severe accidents in LWR and FR. The phenomena include single phase flow of water, supercritical water, helium and sodium, two-phase flow of steam-water or sodium-argon, and multi-phase flows encountered in severe accidents. In this paper, we will summarize current status and future directions of thermal-hydraulic researches at JAEA.

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