Considerations of alloy 617 application in the Gen IV nuclear reactor systems - Part II: Metallurgical property challenges

  • Weiju Ren

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

12 Scopus citations

Abstract

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.

Original languageEnglish
Title of host publicationProceedings of the ASME Pressure Vessels and Piping Conference 2009 - Materials and Fabrication
Pages831-843
Number of pages13
EditionPART A
DOIs
StatePublished - 2010
Event2009 ASME Pressure Vessels and Piping Conference - Prague, Czech Republic
Duration: Jul 26 2009Jul 30 2009

Publication series

NameAmerican Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
NumberPART A
Volume6
ISSN (Print)0277-027X

Conference

Conference2009 ASME Pressure Vessels and Piping Conference
Country/TerritoryCzech Republic
CityPrague
Period07/26/0907/30/09

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