A Study of FIV Characteristics of a Coaxial Double-Tube-Type Cross Vessel for a VHTR

作者：Song Kee Nam^*; Kim Yong Wan; Park Sang Chul

来源：Journal of Nuclear Science and Technology, 2010, 47(6): 542-549.

DOI：10.3327/jnst.47.542

• nuclear hydrogen system
• coaxial double-tube-type cross vessel
• VHTR
• hot gas duct
• flow-induced vibration
• fluid-structure interaction
• structural sizing

A Very High Temperature Gas-Cooled Reactor (VHTR) has been selected as a high-energy heat source of the order of 950 degrees 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 flow-induced vibration (FIV). As an example, a structural sizing of a horizontal HGD with a coaxial double-tube 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 fluid-structure interaction (FSI) analysis of the HGD was carried out using the ADINA code.

• 出版日期2010-6