Volume 6, Issue 5 (May 2009)

    Investigation of Beltline Welding Seam of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel

    (Received 6 June 2008; accepted 18 March 2009)

    Published Online: 2009

    CODEN: JAIOAD

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    Abstract

    The investigation of reactor pressure vessel (RPV) materials from decommissioned nuclear power plants (NPP) offers the unique opportunity to scrutinize the irradiation behavior under real conditions. The paper describes the investigation of trepans taken from the decommissioned WWER-440 RPVs of the Greifswald NPP. The key part of the testing is aimed at the determination of the reference temperature T0 following the ASTM Test Standard E1921 to determine the fracture toughness of the RPV steel in different thickness locations. In a first step, the trepan taken from the RPV Greifswald Unit 1 containing the multilayer welding seam located in the beltline region was investigated. This welding seam represents the irradiated, recovery annealed, and reirradiated condition. It is shown that the Master Curve approach as adopted in ASTM E1921 is applicable to the investigated original WWER-440 weld metal. The evaluated T0 varies through the thickness of the welding seam. After an initial increase of T0 from 10°C at the inner surface to 49°C at 22 mm distance from it, T0 decreases to −32°C at a distance of 70 mm, finally increasing again to 61°C near the outer RPV wall. The lowest T0 value was measured in the root region of the welding seam representing a uniform fine grain ferritic structure. The highest T0 of the weld seam was not measured at the inner wall surface. This is important for the assessment of ductile-to-brittle temperatures measured on subsize Charpy specimens made of weld metal compact samples removed from the inner RPV wall. Our findings imply that these samples do not represent the most conservative condition. Nevertheless, the Charpy transition temperature, TT41J, estimated with results of subsize specimens after the recovery annealing, was confirmed by the testing of standard Charpy V-notch specimens.


    Author Information:

    Viehrig, Hans-Werner
    Forschungszentrum Dresden-Rossendorf, Institute for Safety Research, Department Materials and Components Safety, Dresden,

    Schuhknecht, Jan
    Forschungszentrum Dresden-Rossendorf, Institute for Safety Research, Department Materials and Components Safety, Dresden,

    Rindelhardt, Udo
    Professor, Forschungszentrum Dresden-Rossendorf, Institute for Safety Research, Dresden,

    Weiss, Frank-Peter
    Professor, Forschungszentrum Dresden-Rossendorf, Institute for Safety Research, Dresden,


    Stock #: JAI101925

    ISSN: 1546-962X

    DOI: 10.1520/JAI101925

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    Author
    Title Investigation of Beltline Welding Seam of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel
    Symposium Presented at the ASTM 24th Symposium on Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle, 2008-06-26
    Committee E10