Bypass flow in a prismatic very high temperature gas-cooled nuclear reactor (VHTR) plays
an important role in determining the coolant distribution in the core region. Efficient removal
of heat from the core relies on the majority of coolant passing through the coolant channels
instead of the bypass gaps. Consequently, the bypass flow fraction and its flow characteristic
are important in the design process of the prismatic VHTR. The objective of this study is to
experimentally investigate the flow behavior including the turbulence characteristics inside …