Abstract
In the first paper, two-block crossflow experiments were conducted to develop crossflow coefficient carrelatians, since crossflow, which is inherent in the VHTR(very high-temperature gas-cooled reactor) core, has a significant effect on the core flow distribution.This paper proposes a numerical model with which the global crossflow loss coefficient factors for the parallel and wedge-shaped gaps are calculated. The fuel element crossflow domain was discretized by triangular elements and the pressure distribution in the block interface gap was calculated by the finite element method. The crossflow rate from the periphery of the block to the coolant channels was evaluated from the pressure distribution. The numerical results agreed well with the experimental results. In addition, empirical crossflow equations were devised for the analysis of flow distribution in the VHTR core.
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More From: Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
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