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    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.


    zirconium alloys, nuclear fuel, corrosion, hydriding, stress corrosion, fretting corrosion, pellet-clad mechanical interaction, loss-of-coolant accidents, fuel rod defects, neutron irradiation, zirconium, nuclear materials, nuclear applications, radiation effects

    Author Information:

    Pickman, DO
    UK Atomic Energy Authority, Salwick, Preston, Lancashire

    Committee/Subcommittee: B10.02

    DOI: 10.1520/STP15182S