Journal of the Atomic Energy Society of Japan
Online ISSN : 2433-7285
Print ISSN : 1882-2606
Special Issue
Progress of CFD in nuclear thermal hydraulics
Application to reactor vessel pressure loss evaluation
Tomoaki Ogata, Junichi Takeuchi, Masaaki Okano, Hiroyuki Sakamoto
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Keywords: Pressurized Water Reactor, Computational Fluid Dynamics, Pressure loss, Reactor Vessel, Core Barrel
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2025 Volume 67 Issue 10 Pages 583-587

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[in Japanese]
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© 2025 Atomic Energy Society of Japan
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