Effects of core peripheral components melting on corium pool configuration in lower plenum of acp1000

The Proceedings of the International Conference on Nuclear Engineering (ICONE)(2019)

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Abstract
The MAAP5 code and CFD method are adopted to estimate the melting behavior of core peripheral components for an Advanced China PWR, called ACP1000 after a large break accident to determine the amount of stainless steel relocating into the corium pool. The results suggest that larger portion of peripheral components melting in CFD method because of considering the radiation of fuel rods on shroud and barrel before core melting and ignoring the cooling of steam on the components in core. Effects of different configurations of corium pool on heat flux imposed on the vessel wall are also investigated in this work. The heat flux in light metal layer for the corium pool that obtained by MAAP5 code could be higher than that of CFD case due to its thinner light metal layer.
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Key words
components corium pool configuration,core peripheral components,lower plenum
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