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. This paper, as Part I of the discussion, is focused on the challenges and issues in the mechanical properties of Alloy 617 for the intended nuclear application. Considerations are given in details in its mechanical property data scatter, low creep strength in the desired high temperature range, lack of long-term creep curves, high loading rate dependency, and preponderant tertiary creep. Some research and development activities are suggested with discussions on their viability to satisfy the Gen IV Nuclear Reactor Systems needs in near future and in the long run.
Skip Nav Destination
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 I—Mechanical Property Challenges
Weiju Ren
Weiju Ren
Oak Ridge National Laboratory, Oak Ridge, TN
Search for other works by this author on:
Weiju Ren
Oak Ridge National Laboratory, Oak Ridge, TN
Paper No:
PVP2009-77313, pp. 781-794; 14 pages
Published Online:
July 9, 2010
Citation
Ren, W. "Considerations of Alloy 617 Application in the Gen IV Nuclear Reactor Systems: Part I—Mechanical 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. 781-794. ASME. https://doi.org/10.1115/PVP2009-77313
Download citation file:
21
Views
Related Proceedings Papers
Related Articles
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)
A Review Paper on Aging Effects in Alloy 617 for Gen IV Nuclear Reactor Applications
J. Pressure Vessel Technol (April,2009)
High-Temperature Performance of Cast CF8C-Plus Austenitic Stainless Steel
J. Eng. Gas Turbines Power (September,2011)
Related Chapters
Blends and Alloys
Introduction to Plastics Engineering
Studies Performed
Closed-Cycle Gas Turbines: Operating Experience and Future Potential
Basic Concepts
Design & Analysis of ASME Boiler and Pressure Vessel Components in the Creep Range