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

    If you are an ASTM Compass Subscriber and this document is part of your subscription, you can access it for free at ASTM Compass
    STP1270

    Fracture Toughness Test Results of Thermal Aged Reactor Vessel Materials

    Published: 01 January 1996


      Format Pages Price  
    PDF (180K) 10 $25   ADD TO CART
    Complete Source PDF (22M) 1161 $180   ADD TO CART

    Cite this document

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


    Abstract

    Thermal-aged surveillance materials consisting of SA-533, Grade B, Class 1 plate material; SA-508, Class 2 forging material; and 2 Mn-Mo-Ni/Linde 80 weld metals were removed from two commercial reactor pressure vessels. The material from the first reactor vessel received a thermal exposure of approximately 103,000 hours at 282°C (540°F), while the material from the second reactor vessel received a thermal exposure of approximately 93,000 hours at 282°C (540°F). Tensile and 1/2T compact fracture toughness specimens were fabricated from these materials and tested. In addition, to examine the effects of annealing, selected thermal-aged and unaged specimens were annealed at 454°C (850°F) and tested. Varying responses in the fracture toughness properties were observed for all materials after exposure to the thermal-aging temperature. The base metal plate had an observed decrease in J-values after its respective aging exposure, while no significant difference in the J-values were observed for the Linde 80 weld metals. No significant difference was seen in the J-data for the aged/annealed materials, but because of the small number of test specimens available, no conclusion could be determined for the response to annealing.

    Keywords:

    thermal aging, reactor vessel materials, SA-533 Gr. B1 plate, SA-508, Class 2 forging, submerged-arc weld


    Author Information:

    DeVan, MJ
    Engineer, B&W Nuclear Technologies Inc., Lynchburg, VA

    Lowe, AL
    Retired Advisory Engineer, B&W Nuclear Technologies Inc., Lynchburg, VA

    Hall, JB
    Research Engineer, Materials Performance, The Babcock & Wilcox Company, Alliance, OH


    Committee/Subcommittee: E10.02

    DOI: 10.1520/STP16500S