Volume 3, Issue 2 (February 2006)

    Mechanical Property Changes in Reactor Vessel Materials Thermally Aged for 209 000 H at 260°C

    (Received 27 May 2004; accepted 31 August 2005)

    Published Online: 2007

    CODEN: JAIOAD

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    Abstract

    Surveillance materials consisting of a SA-508 Class 2 forging, a Mn–Mo–Ni Linde 80 submerged-arc weld, and an SA-533, Grade B, Class 1, correlation monitor material were thermally aged on a commercial reactor pressure vessel. The materials were exposed to a thermal environment of 260°C for 209000h. This temperature is below the range (minimum of 370°C) where the effects of long-term thermal aging are typically considered relevant. Charpy impact, master curve transition temperature, upper-shelf fracture toughness, and tensile testing were conducted to evaluate the long-term thermal aging changes in material properties. Small changes in the impact properties were observed for all the materials, but were generally within the 95 % confidence bounds for typical Charpy data. Upper-shelf energy also showed small variations, but a general decrease for all materials was not seen. Fracture toughness testing at the upper shelf indicated that the upper-shelf toughness had increased, however the data is scattered. Master curve T0 testing in the transition region showed little change in the forging and plate results; however an improvement in the transition temperature of the weld metal was measured.


    Author Information:

    Gunawardane, Heshan P.
    Engineer, Materials and Structural Analysis, AREVA, Lynchburg, VA

    Hall, J. Brian
    Engineer, Materials and Structural Analysis, AREVA, Lynchburg, VA

    Rosinski, Stan T.
    Project Manager, EPRI, Charlotte, NC


    Stock #: JAI12430

    ISSN: 1546-962X

    DOI: 10.1520/JAI12430

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    Author
    Title Mechanical Property Changes in Reactor Vessel Materials Thermally Aged for 209 000 H at 260°C
    Symposium Effects of Radiation on Materials, 2004-06-10
    Committee E10