Alloy 800H is currently under consideration for applications in the Next Generation Nuclear Plant at operational temperatures above 750°C. To provide supporting information in this paper at the attempt to facilitate the consideration, service requirements of the nuclear system for structural materials is first described; and then an extensive review of Alloy 800H is given on its codification with respect to development and research history, mechanical behavior and design allowables, metallurgical aging resistance, environmental effect considerations, data requirements and availability, weldments, as well as many other aspects relevant to the intended nuclear application; an finally further research and development activities to support the materials qualification are suggested.
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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:
978-0-7918-49255
PROCEEDINGS PAPER
A Review of Alloy 800H for Applications in the Gen IV Nuclear Energy Systems
Weiju Ren,
Weiju Ren
Oak Ridge National Lab, Oak Ridge, TN
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Robert Swindeman
Robert Swindeman
Cromtech, Oak Ridge, TN
Search for other works by this author on:
Weiju Ren
Oak Ridge National Lab, Oak Ridge, TN
Robert Swindeman
Cromtech, Oak Ridge, TN
Paper No:
PVP2010-25278, pp. 821-836; 16 pages
Published Online:
January 10, 2011
Citation
Ren, W, & Swindeman, R. "A Review of Alloy 800H for Applications in the Gen IV Nuclear Energy Systems." Proceedings of the ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B. Bellevue, Washington, USA. July 18–22, 2010. pp. 821-836. ASME. https://doi.org/10.1115/PVP2010-25278
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