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      저자 : Funatani Shumpei (검색결과 2 건)
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        Comparison on Safety Features among HTGR’s Reactor Cavity Cooling Systems (RCCSs)

        Takamatsu Kuniyoshi,Funatani Shumpei 한국원자력학회 2024 Nuclear Engineering and Technology Vol.56 No.3

        Reactor cavity cooling systems (RCCSs) comprising passive safety features use the atmosphere as a coolant, which cannot be lost. However, their drawback is that they are easily affected by atmospheric disturbances. To realize the commercial application of the two types of passive RCCSs, namely RCCSs based on atmospheric radiation and atmospheric natural circulation, their safety must be evaluated, that is, they must be able to remove heat from the reactor pressure vessel (RPV) surface at all times and under any condition other than under normal operating conditions. These include both expected and unexpected natural phenomena and accidents. Moreover, they must be able to eliminate the heat leakage emitted from the RPV surface during normal operation. However, utilizing all of the heat emitted from the RPV surface increases the degree of waste heat utilization. This study aims to understand the characteristics and degree of passive safety features for heat removal by comparing RCCSs based on atmospheric radiation and atmospheric natural circulation under the same conditions. It was concluded that the proposed RCCS based on atmospheric radiation has an advantage in that the temperature of the RPV could be stably maintained against disturbances in the ambient air.

      • KCI등재

        STUDY ON HEAT TRANSFER CHARACTERISTICS OF THE ONE SIDE-HEATED VERTICAL CHANNEL WITH INSERTED POROUS MATERIALS APPLIED AS A VESSEL COOLING SYSTEM

        SHINJI KURIYAMA,TETSUAKI TAKEDA,SHUMPEI FUNATANI 한국원자력학회 2015 Nuclear Engineering and Technology Vol.47 No.5

        In the very high temperature reactor (VHTR), which is a next generation nuclear reactorsystem, ceramics are used as a fuel coating material and graphite is used as a core structuralmaterial. Even if a depressurization accident occurs and the reactor power goes up instantly,the temperature of the core will change only slowly. This is because the thermal capacity ofthe core is so high. Therefore, the VHTR system can passively remove the decay heat of thecore by natural convection and radiation from the surface of the reactor pressure vessel. Theobjectives of this study are to investigate the heat transfer characteristics of natural convectionof a one-side heated vertical channel with inserted porous materials of high porosityand also to develop the passive cooling system for the VHTR. An experiment was carried outusing a one-side heated vertical rectangular channel. To obtain the heat transfer and fluidflow characteristics of the vertical channel with inserted porous material, we have alsocarried out a numerical analysis using a commercial Computational Fluid Dynamics (CFD)code. This paper describes the thermal performances of the one-side heated vertical rectangularchannel with an inserted copper wire of high porosity.

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