Mechanistic understanding of zirconium alloy fuel cladding performance

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

A review is presented of work performed in our group over the years in the areas of radiation damage, corrosion, hydrogen pickup, hydriding, and the mechanical behavior of zirconium alloy nuclear fuel cladding with the goal of developing a greater mechanistic understanding of cladding performance in service.

Original languageEnglish (US)
Title of host publicationZirconium in the Nuclear Industry
Subtitle of host publication18th International Symposium
EditorsRobert J. Comstock, Arthur T. Motta
PublisherASTM International
Pages19-51
Number of pages33
ISBN (Electronic)9780803176416
DOIs
StatePublished - Jan 1 2018
Event18th International Symposium on Zirconium in the Nuclear Industry - Hilton Head, United States
Duration: May 15 2016May 19 2016

Publication series

NameASTM Special Technical Publication
VolumeSTP 1597
ISSN (Print)0066-0558

Other

Other18th International Symposium on Zirconium in the Nuclear Industry
CountryUnited States
CityHilton Head
Period5/15/165/19/16

All Science Journal Classification (ASJC) codes

  • Materials Science(all)

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