SYMPOSIA PAPER Published: 01 February 2018
STP159720160095

Mechanistic Understanding of Zirconium Alloy Fuel Cladding Performance

Source

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 Information

Motta, Arthur, T.
Pennsylvania State University, Dept. of Mechanical and Nuclear Engineering, University Park, PA, US
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Details
Developed by Committee: B10
Pages: 19–51
DOI: 10.1520/STP159720160095
ISBN-EB: 978-0-8031-7642-3
ISBN-13: 978-0-8031-7641-6