You are being redirected because this document is part of your ASTM Compass® subscription.
    This document is part of your ASTM Compass® subscription.


    Mechanical Property Changes in Reactor Vessel Materials Thermally Aged for 209000 H at 282 °C


      Format Pages Price  
    PDF (388K) 9 $25   ADD TO CART
    Complete Source PDF (17M) 406 $98   ADD TO CART

    Cite this document

    X Add email address send
      .RIS For RefWorks, EndNote, ProCite, Reference Manager, Zoteo, and many others.   .DOCX For Microsoft Word


    Surveillance materials consisting of a SA-508 Class 2 forging, a Mn-Mc-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 282°C for 209 000 h. 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.


    thermal aging, reactor vessel materials, Charpy, fracture toughness, transition, temperature, tensile

    Author Information:

    Gunawardane, HP
    Engineer, Materials and Structural Analysis, AREVA, Lynchburg, VA

    Hall, BJ
    Engineer, Materials and Structural Analysis, AREVA, Lynchburg, VA

    Rosinski, ST
    Project Manager, EPRI, Charlotte, NC

    Committee/Subcommittee: E10.05

    DOI: 10.1520/STP37581S