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

    Published: Jan 2010

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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 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.

    Keywords:

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


    Author Information:

    Pickman, David O.
    UK Atomic Energy Authority, Salwick, Preston, Lancashire


    Paper ID: MNL12114R

    Committee/Subcommittee: B10.02

    DOI: 10.1520/MNL12114R


    CrossRef ASTM International is a member of CrossRef.

    ISBN10:
    ISBN13: 978-0-8031-7018-6