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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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