STP1245

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

    Published: Jan 1994


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    Abstract

    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.

    Keywords:

    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


    Paper ID: STP15182S

    Committee/Subcommittee: B10.02

    DOI: 10.1520/STP15182S


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