MANUAL Published: 01 January 2010
MNL12114R

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 defect, including hydride defects and fretting corrosion, are discussed. The original paper was published by ASTM International in STP 1245, Zirconium in the Nuclear Industry: Tenth International Symposium, 1994, pp. 19–32.

Author Information

Pickman, David, O.
UK Atomic Energy Authority, Salwick, Preston, Lancashire, UK
Price: Free
Contact Sales
Related
Reprints and Permissions
Reprints and copyright permissions can be requested through the
Copyright Clearance Center
Details
Developed by Committee: B10
Pages: 215–228
DOI: 10.1520/MNL12114R
ISBN-EB: 978-0-8031-8421-3
ISBN-13: 978-0-8031-7018-6