Abstract
A Very High Temperature Gas-Cooled Reactor (VHTR) has been selected as a high-energy heat source of the order of 950°C for nuclear hydrogen generation, which can produce hydrogen from water or natural gas. A primary hot gas duct (HGD) as a coaxial double-tube-type cross vessel is a key component connecting a reactor pressure vessel and an intermediate heat exchanger in the VHTR. In this study, a structural sizing methodology for the primary HGD of a VHTR is proposed in order to modulate a flowinduced vibration (FIV). As an example, a structural sizing of a horizontal HGD with a coaxial doubletube structure was carried out using the proposed method. These activities include deciding the geometric dimensions, selecting the material, and evaluating the strength of the coaxial double-tube-type cross vessel components. Also, in order to compare the FIV characteristics of the proposed design cases, a fluidstructure interaction (FSI) analysis of the HGD was carried out using the ADINA code.
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