Mechanistic Understanding of Zirconium Alloy Fuel Cladding Performance

Arthur Motta

doi:10.1520/STP159720160095

SYMPOSIA PAPER Published: 01 February 2018

STP159720160095

Mechanistic Understanding of Zirconium Alloy Fuel Cladding Performance

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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

Mechanistic Understanding of Zirconium Alloy Fuel Cladding Performance

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