A process heat exchanger (PHE) transfers the heat generated from a nuclear reactor to a sulfur-iodine hydrogen production system in the NHDD (Nuclear Hydrogen Development and Demonstration), and was subjected to very high temperature up to 950°C. An evaluation of creep-fatigue damage, for a prototype PHE, has been carried out from finite element analysis with the full three dimensional model of the PHE. The inlet temperature in the primary side of the PHE was 950°C with an internal pressure of 7MPa while the inlet temperature in the secondary side of the PHE is 500°C with internal pressure of 4MPa. The candidate materials of the PHE were Alloy 617 and Hastelloy X. In this study, only the Alloy 617 was considered because the high temperature design code is available only for Alloy 617. Using the full 3D finite element analysis on the PHE model, creep-fatigue damage evaluation at very high temperature was carried out, according to the ASME Draft Code Case for Alloy 617, and technical issues in the draft Code Case were raised.
Skip Nav Destination
ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference
July 18–22, 2010
Bellevue, Washington, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-4920-0
PROCEEDINGS PAPER
Evaluation of Creep-Fatigue Damage for Prototype Process Heat Exchanger of the NHDD Plant
Hyeong-Yeon Lee,
Hyeong-Yeon Lee
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Search for other works by this author on:
Kee-Nam Song,
Kee-Nam Song
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Search for other works by this author on:
Yong-Wan Kim,
Yong-Wan Kim
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Search for other works by this author on:
Sung-Deok Hong,
Sung-Deok Hong
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Search for other works by this author on:
Hong-Yune Park
Hong-Yune Park
AD-Solution Co., Ltd., Daejeon, Republic of Korea
Search for other works by this author on:
Hyeong-Yeon Lee
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Kee-Nam Song
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Yong-Wan Kim
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Sung-Deok Hong
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Hong-Yune Park
AD-Solution Co., Ltd., Daejeon, Republic of Korea
Paper No:
PVP2010-25354, pp. 307-313; 7 pages
Published Online:
January 10, 2011
Citation
Lee, H, Song, K, Kim, Y, Hong, S, & Park, H. "Evaluation of Creep-Fatigue Damage for Prototype Process Heat Exchanger of the NHDD Plant." Proceedings of the ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASME 2010 Pressure Vessels and Piping Conference: Volume 1. Bellevue, Washington, USA. July 18–22, 2010. pp. 307-313. ASME. https://doi.org/10.1115/PVP2010-25354
Download citation file:
9
Views
Related Proceedings Papers
Related Articles
An Evaluation of Creep-Fatigue Damage for the Prototype Process Heat Exchanger of the NHDD Plant
J. Pressure Vessel Technol (October,2011)
Conceptual Structure Design of High Temperature Isolation Valve for High Temperature Gas Cooled Reactor
J. Eng. Gas Turbines Power (November,2011)
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 Chapters
Compressive Deformation of Hot-Applied Rubberized Asphalt Waterproofing
Roofing Research and Standards Development: 10th Volume
New Generation Reactors
Energy and Power Generation Handbook: Established and Emerging Technologies
Introduction
Consensus on Operating Practices for Control of Water and Steam Chemistry in Combined Cycle and Cogeneration