Fracture Toughness Test Results of Thermal Aged Reactor Vessel Materials

    Published: Jan 1996

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    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.


    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

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