Zirconium alloy performance in light water reactors: A review of UK and Scandinavian experience

Conference · Sat Dec 31 00:00:00 EST 1994

OSTI ID:55645

Pickman, D O ^[1]

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1. UK Atomic Energy Authority, Preston (United Kingdom)

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.

• OSTI ID: 55645
• Report Number(s): CONF-930611-; ISBN 0-8031-2011-7; TRN: 95:012890
• Resource Relation: Conference: 10. international symposium on zirconium in the nuclear industry, Baltimore, MD (United States), 21-24 Jun 1993; Other Information: PBD: 1994; Related Information: Is Part Of Zirconium in the nuclear industry: Tenth international symposium. ASTM STP 1245; Garde, A.M.; Bradley, E.R. [eds.]; PB: 818 p.
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
ZIRCONIUM ALLOYS
PERFORMANCE
WATER COOLED REACTORS
LOSS OF COOLANT
FUEL CANS
REACTOR MATERIALS
NUCLEAR FUELS
PHYSICAL RADIATION EFFECTS
HYDRIDATION
STRESS CORROSION
CRACK PROPAGATION
FUEL RODS
FUEL-CLADDING INTERACTIONS