Sodium experiments on core thermal hydraulics

Kamide, Hideki

Sodium experiments on core thermal hydraulics carried out in JAEA are introduced as candidates of the next IAEA Coordinated Research Project. Inter-wrapper flow (IWF) is known as natural convection in sodium gap between subassemblies in SFR core due to buoyancy force of cold sodium provided by dipped heat exchanger of DRACS in reactor upper plenum. Sodium experiments on IWF were carried out in this study and thermal hydraulics in the subassemblies and inter-wrapper gaps was clarified.

Language	:	English
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Meeting title	:	4th Research Coordination Meeting (RCM) of the IAEA Coordinated Research Project on Benchmark Analyses of Sodium Natural Convection in the Upper Plenum of the MONJU Reactor Vessel
Held date	:	2012/04
Location (city)	:	Tsuruga
Location (country)	:	Japan
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Keywords	:	no keyword
Research Facility	:	プラント過渡応答試験装置
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Registration No. : BB20120096
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