Experimental and CFD studies of the bypass flow in a prismatic core of VHTR using a small-scale model
W Kanjanakijkasem, H Wang… - Progress in Nuclear …, 2016 - Elsevier
The bypass flow in a prismatic very high temperature reactor (VHTR) core is an important
parameter in reactor design, which has not been well assessed in publications to date. To
rectify this deficit and evaluate the bypass flow fraction in a VHTR core, experiments were
conducted using a small-scale model for a portion of a prismatic core of VHTR with air as the
working fluid. Bypass flow simulations were performed using STAR-CCM+ software to
validate the code by comparing basic physical quantities related to bypass flow to each …
parameter in reactor design, which has not been well assessed in publications to date. To
rectify this deficit and evaluate the bypass flow fraction in a VHTR core, experiments were
conducted using a small-scale model for a portion of a prismatic core of VHTR with air as the
working fluid. Bypass flow simulations were performed using STAR-CCM+ software to
validate the code by comparing basic physical quantities related to bypass flow to each …
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