The 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 the reactor pressure vessel and the intermediate heat exchanger in a VHTR. In this study, a structural sizing methodology for the primary HGD of a VHTR is suggested in order to modulate a flow-induced vibration (FIV). And as an example, a structural sizing of a horizontal HGD with a coaxial double-tube structure was carried out using the suggested method. These activities include a decision of the geometric dimensions, a selection of the material, and a evaluation of 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 on a quarter part of the HGD was carried out using the ADINA code.
Skip Nav Destination
17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4351-2
PROCEEDINGS PAPER
Analysis of FIV Characteristics on a Coaxial Double-Tube Type Hot Gas Duct for the VHTR
Kee-nam Song,
Kee-nam Song
Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
Search for other works by this author on:
Yong-wan Kim,
Yong-wan Kim
Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
Search for other works by this author on:
S.-C. Park
S.-C. Park
AbleMAX, Inc., Seoul, Republic of Korea
Search for other works by this author on:
Kee-nam Song
Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
Yong-wan Kim
Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
S.-C. Park
AbleMAX, Inc., Seoul, Republic of Korea
Paper No:
ICONE17-75007, pp. 779-785; 7 pages
Published Online:
February 25, 2010
Citation
Song, K, Kim, Y, & Park, S. "Analysis of FIV Characteristics on a Coaxial Double-Tube Type Hot Gas Duct for the VHTR." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems. Brussels, Belgium. July 12–16, 2009. pp. 779-785. ASME. https://doi.org/10.1115/ICONE17-75007
Download citation file:
10
Views
Related Proceedings Papers
Related Articles
Radiation Effects on Heat Transfer in the Reactor Core and Heat Exchangers of an HTGR
J. Heat Transfer (August,1975)
TRU-Fueled Very High Temperature Reactors for Applications Requiring an Extended Operation With Minimized Control and No Refueling
J. Eng. Gas Turbines Power (September,2009)
Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods
ASME J of Nuclear Rad Sci (July,2024)
Related Chapters
Nuclear Components Operating in the Creep Regime
Analysis of ASME Boiler, Pressure Vessel, and Nuclear Components in the Creep Range
New Generation Reactors
Energy and Power Generation Handbook: Established and Emerging Technologies
Design Analysis of Steel Concrete Composite Vessel for Stationary Storage of High-Pressure Hydrogen
International Hydrogen Conference (IHC 2012): Hydrogen-Materials Interactions