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

Weiju Ren

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

7 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. 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.

Original languageEnglish
Title of host publicationProceedings of the ASME Pressure Vessels and Piping Conference 2009 - Materials and Fabrication
Pages781-794
Number of pages14
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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