Published July 1, 2009 | Version v1
Miscellaneous

Considerations of Alloy 617 Application in the Gen IV Nuclear Reactor Systems Part II: Metallurgical Property Challenges

  • 1. Oak Ridge National Laboratory, TN (United States)

Description

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

Availability note (English)

Available from Oak Ridge National Laboratory, Oak Ridge, TN (US)

Additional details

Publishing Information

Imprint Pagination
vp.

Conference

Title
2009 ASME Pressure Vessels and Piping Division Conference
Dates
26-30 Jul 2009
Place
Prague (Czech Republic)

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