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

DO Pickman

doi:10.1520/STP15182S

SYMPOSIA PAPER Published: 01 January 1994

STP15182S

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

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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

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

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