Alloy 617 is currently considered as a leading candidate material for high temperature components in the Gen IV Nuclear Reactor Systems. Because of the unprecedented severe working conditions beyond its commercial service experience required by the Gen IV systems, the alloy faces various challenges in both mechanical and metallurgical properties. Following a previous paper discussing the mechanical property challenges, this paper is focused on the challenges and issues in metallurgical properties of the alloy for the intended nuclear application. Considerations are given in details about its metallurgical stability and aging evolution, aging effects on mechanical properties, potential Co hazard, and internal oxidation. Some research and development activities are suggested with discussions on viability to satisfy the Gen IV Nuclear Reactor System needs.
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ASME 2009 Pressure Vessels and Piping Conference
July 26–30, 2009
Prague, Czech Republic
Conference Sponsors:
- Pressure Vessels and Piping
ISBN:
978-0-7918-4369-7
PROCEEDINGS PAPER
Considerations of Alloy 617 Application in the Gen IV Nuclear Reactor Systems: Part II—Metallurgical Property Challenges
Weiju Ren
Weiju Ren
Oak Ridge National Laboratory, Oak Ridge, TN
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Weiju Ren
Oak Ridge National Laboratory, Oak Ridge, TN
Paper No:
PVP2009-78146, pp. 831-843; 13 pages
Published Online:
July 9, 2010
Citation
Ren, W. "Considerations of Alloy 617 Application in the Gen IV Nuclear Reactor Systems: Part II—Metallurgical Property Challenges." Proceedings of the ASME 2009 Pressure Vessels and Piping Conference. Volume 6: Materials and Fabrication, Parts A and B. Prague, Czech Republic. July 26–30, 2009. pp. 831-843. ASME. https://doi.org/10.1115/PVP2009-78146
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