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Na, Hanbee,Kim, Hyung Sop,Lee, Hee Joon,Kim, Do Sam,Kwon, Sejin Elsevier 2017 Progress in nuclear energy Vol.97 No.-
<P><B>Abstract</B></P> <P>This preliminary study examines the feasibility of adopting a post-flooding strategy as molten corium cooling for APR1400 plants. We address negative effects of a steam explosion and unevenly spread corium that are associated with the current pre-flooded cavity strategies. In this research, we assess the feasibility of the post-flooding strategy in two steps. First, we use three-dimensional (3D) CFD methodology to simulate molten corium spreading in the dry cavity of an APR1400 plant. In the second step, we perform ablation depth analysis with respect to the time taken to flood the cavity, based on OECD/MCCI project results with safety margin. The CFD simulation shows molten corium to be evenly spread in a uniform thickness of about 35 cm in the dry cavity. Our analysis results indicate that the integrity of the steel liner beneath the sacrificial concrete can be maintained during ex-vessel corium cooling if water is supplied into the cavity within 7.4 h of the vessel being breached. Therefore, the CFD corium spreading simulations and the leak tightness assessment confirms the feasibility of adopting the post-flooding strategy of molten corium cooling for APR1400 plants evading the risks of steam explosion.</P> <P><B>Highlights</B></P> <P> <UL> <LI> Negative effects caused by pre-flooded cavity strategies are reviewed. </LI> <LI> 3-Dimensional CFD simulations of molten corium spreading for APR1400 plants show the even distribution in dry cavity. </LI> <LI> Axial concrete ablation analysis of APR1400 SKs 5 & 6 is conducted based on OECD/MCCI project results. </LI> <LI> The feasibility study of the post-flooding strategy as molten corium cooling of APR1400 SKs 5 & 6 is conducted. </LI> </UL> </P>
Ajith Krishnan R,Zhong Han Chai,Hanbee Na,Hee Joon Lee 대한기계학회 2021 JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY Vol.35 No.7
Flow boiling experiments in microchannels under low mass fluxes have rarely been reported in the literature. In this study, flow boiling critical heat flux (CHF) for a parallel straight copper microchannel heat sink with 41 channels and hydraulic diameter of 420 µm (width: 300 µm; height: 700 µm) is reported under low mass fluxes(< 100 kg/m 2 s). The flow patterns reveal that the inertial force will be too low to flush the bubble downstream. The heat transfer coefficient was observed to decrease with an increase in the heat flux or vapor quality, which pointed toward convective boiling dominancy inside the channels. When approaching the CHF, the vapor flowed back to the heat sink's inlet plenum, resulting in a flow blockage, which is the main factor for the CHF occurrence.