Title: Corrosion of Zirconium Alloys
Publisher: Elsevier
Publication Year: 2012
JRC N°: JRC69383
ISBN: 978-0-08-056027-4
URI: http://publications.jrc.ec.europa.eu/repository/handle/JRC69383
Type: Articles in periodicals and books
Abstract: Zirconium alloys are widely used for fuel cladding and in pressure tubes, fuel channels (boxes), and fuel spacer grids in almost all water-cooled reactors: light water reactors such as the pressurized water reactor (PWR) and the boiling water reactor (BWR) as well as the Canadian designed Canadian Deuterium Uranium (CANDU) heavy water reactor. Since its employment in the first commercial nuclear power plant (Shippingport) in the 1960s, Zircaloy, a zirconium–tin alloy, has shown satisfactory behavior during many decades. However, degradation due to waterside corrosion can limit the in-reactor design life of the nuclear fuel.
JRC Directorate:Nuclear Safety and Security

Files in This Item:
There are no files associated with this item.

Items in repository are protected by copyright, with all rights reserved, unless otherwise indicated.