@inproceedings{ec7af4a24f94466f9bec4335a0dc8e49,
title = "Mechanistic understanding of zirconium alloy fuel cladding performance",
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.",
author = "Motta, {Arthur T.}",
note = "Publisher Copyright: Copyright {\textcopyright} 2018 by ASTM International.; 18th International Symposium on Zirconium in the Nuclear Industry ; Conference date: 15-05-2016 Through 19-05-2016",
year = "2018",
doi = "10.1520/STP159720160095",
language = "English (US)",
series = "ASTM Special Technical Publication",
publisher = "ASTM International",
pages = "19--51",
editor = "Comstock, {Robert J.} and Motta, {Arthur T.}",
booktitle = "Zirconium in the Nuclear Industry",
}