Evaluation of creep-fatigue damage has been carried out for the hot gas duct (HGD) structure in the nuclear hydrogen development and demonstration (NHDD) plant. The core outlet and inlet temperature of the NHDD plant are and , respectively. Case studies on high temperature design codes of the draft code case for Alloy 617, ASME boiler and pressure vessel code section III subsection NH (ASME-NH), and RCC-MR were carried out for the inner tube of the HGD for the candidate materials of Alloy 617 and Alloy 800H. Technical issues in application of the draft code case to a high temperature structure are discussed for the Alloy 617 material. Code comparison between the ASME-NH and RCC-MR for Alloy 800H has been carried out. The candidate material of the outer pressure boundary (cross vessel) of the HGD is Mod.9Cr-1Mo steel. The damage evaluation, according to the ASME-NH and RCC-MR for the cross vessel of Mod.9Cr-1Mo steel, has been conducted and their results were compared.
Skip Nav Destination
e-mail: hylee@kaeri.re.kr
Article navigation
June 2010
Research Papers
Evaluation of Creep-Fatigue Damage for Hot Gas Duct Structure of the NHDD Plant
Hyeong-Yeon Lee,
e-mail: hylee@kaeri.re.kr
Hyeong-Yeon Lee
Korea Atomic Energy Research Institute
, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Korea
Search for other works by this author on:
Kee-Nam Song,
Kee-Nam Song
Korea Atomic Energy Research Institute
, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Korea
Search for other works by this author on:
Yong-Wan Kim
Yong-Wan Kim
Korea Atomic Energy Research Institute
, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Korea
Search for other works by this author on:
Hyeong-Yeon Lee
Korea Atomic Energy Research Institute
, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Koreae-mail: hylee@kaeri.re.kr
Kee-Nam Song
Korea Atomic Energy Research Institute
, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Korea
Yong-Wan Kim
Korea Atomic Energy Research Institute
, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, KoreaJ. Pressure Vessel Technol. Jun 2010, 132(3): 031101 (8 pages)
Published Online: May 4, 2010
Article history
Received:
April 14, 2009
Revised:
November 6, 2009
Online:
May 4, 2010
Published:
May 4, 2010
Citation
Lee, H., Song, K., and Kim, Y. (May 4, 2010). "Evaluation of Creep-Fatigue Damage for Hot Gas Duct Structure of the NHDD Plant." ASME. J. Pressure Vessel Technol. June 2010; 132(3): 031101. https://doi.org/10.1115/1.4000728
Download citation file:
Get Email Alerts
Experimental Research on Thermal-Oxidative Aging Performance of Polyethylene Pipe Under Hydrostatic Pressure
J. Pressure Vessel Technol
The upper bound of the buckling stress of axially compressed carbon steel circular cylindrical shells
J. Pressure Vessel Technol
Dynamics Modeling and Analysis of Small-Diameter Pipeline Inspection Gauge during Passing Through Elbow
J. Pressure Vessel Technol
Prestressing Estimation for Multilayer Clamping High Pressure Vessel Laminates
J. Pressure Vessel Technol (October 2024)
Related Articles
An Evaluation of Creep-Fatigue Damage for the Prototype Process Heat Exchanger of the NHDD Plant
J. Pressure Vessel Technol (October,2011)
A Review Paper on Aging Effects in Alloy 617 for Gen IV Nuclear Reactor Applications
J. Pressure Vessel Technol (April,2009)
Failure Mechanisms of High Temperature Components in Power Plants
J. Eng. Mater. Technol (July,2000)
A Review on Current Status of Alloys 617 and 230 for Gen IV Nuclear Reactor Internals and Heat Exchangers
J. Pressure Vessel Technol (August,2009)
Related Proceedings Papers
Related Chapters
Lessons Learned: NRC Experience
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards
Creep Fatigue Behavior of Creep Strength Enhanced Ferritic Steels
Creep-Fatigue Interactions: Test Methods and Models
Research on Fatigue of Cr-Mo Steel for Hydrogen Storage Vessels
International Hydrogen Conference (IHC 2016): Materials Performance in Hydrogen Environments