SYMPOSIA PAPER Published: 01 January 1994
STP15182S

Zirconium Alloy Performance in Light Water Reactors: A Review of UK and Scandinavian Experience

Source

Various aspects of zirconium alloy development for light water reactors in the UK and Scandinavia are reviewed, including the contribution made by some unique nuclear testing facilities. Among the problems encountered were the irradiation enhancement of corrosion and hydrogen pickup, crud deposition, iodine-induced stress-corrosion cracking on power ramping, and severe cladding deformation in loss-of-coolant accident conditions. The causes and behavior of defects, including hydride defects and fretting corrosion, are discussed.

Author Information

Pickman, DO
UK Atomic Energy Authority, Salwick, Preston, Lancashire, UK
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Details
Developed by Committee: B10
Pages: 19–32
DOI: 10.1520/STP15182S
ISBN-EB: 978-0-8031-5286-1
ISBN-13: 978-0-8031-2011-2