Transactions of the Korean Society of Pressure Vessels and Piping (한국압력기기공학회 논문집)
- Volume 4 Issue 2
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- Pages.1-6
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- 2008
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- 1738-8333(pISSN)
Preliminary Structural Sizing of the Co-axial Double-tube Type Primary Hot Gas Duct for the Nuclear Hydrogen Reactor
수소생산용 원자로에서 동심축 이중관형 1차 고온가스덕트의 예비 구조정산
Abstract
Very High Temperature Gas Cooled Reactor (VHTR) has been selected as a high energy heat source for nuclear hydrogen generation. The VHTR can produce hydrogen from heat and water by using a thermo-chemical process or from heat, water, and natural gas by steam reformer technology. A co-axial double-tube primary hot gas duct (HGD) is a key component connecting the reactor pressure vessel and the intermediate heat exchanger (IHX) for the VHTR. In this study, a preliminary design analysis for the primary HGD of the nuclear hydrogen system was carried out. These preliminary design activities include a determination of the size, a strength evaluation and an appropriate material selection. The determination of the size was undertaken based on various engineering concepts, such as a constant flow velocity model, a constant flow rate model, a constant hydraulic head model, and finally a heat balanced model.