A review of alloy 800H for applications in the gen IV nuclear energy systems

Weiju Ren, Robert Swindeman

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

32 Scopus citations

Abstract

Alloy 800H is currently under consideration for applications in the Next Generation Nuclear Plant at operational temperatures above 750°C. To provide supporting information in this paper at the attempt to facilitate the consideration, service requirements of the nuclear system for structural materials is first described; and then an extensive review of Alloy 800H is given on its codification with respect to development and research history, mechanical behavior and design allowables, metallurgical aging resistance, environmental effect considerations, data requirements and availability, weldments, as well as many other aspects relevant to the intended nuclear application; an finally further research and development activities to support the materials qualification are suggested.

Original languageEnglish
Title of host publicationAmerican Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
Pages821-836
Number of pages16
DOIs
StatePublished - 2010
EventASME 2010 Pressure Vessels and Piping Division/K-PVP Conference, PVP2010 - Bellevue, WA, United States
Duration: Jul 18 2010Jul 22 2010

Publication series

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

Conference

ConferenceASME 2010 Pressure Vessels and Piping Division/K-PVP Conference, PVP2010
Country/TerritoryUnited States
CityBellevue, WA
Period07/18/1007/22/10

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