STP1270: Fracture Toughness of Irradiated Candidate Materials for ITER First Wall/Blanket Structures

    Alexander, DJ
    Oak Ridge National Laboratory, Oak Ridge, TN

    Pawel, JE
    Oak Ridge National Laboratory, Oak Ridge, TN

    Grossbeck, ML
    Oak Ridge National Laboratory, Oak Ridge, TN

    Rowcliffe, AF
    Oak Ridge National Laboratory, Oak Ridge, TN

    Shiba, K
    Japan Atomic Energy Research Institute, Tokai-Mura,

    Pages: 26    Published: Jan 1996


    Abstract

    Disk compact specimens of candidate materials for first wall/blanket structures in ITER have been irradiated to damage levels of about 3 dpa at nominal irradiation temperatures of either 90 or 250°C. These specimens have been tested over a temperature range from 20 to 250°C to determine J-integral values and tearing moduli. The results show that irradiation at these temperatures reduces the fracture toughness of austenitic stainless steels, but the toughness remains quite high. The toughness decreases as the test temperature increases. Irradiation at 250°C is more damaging than at 90°C, causing larger decreases in the fracture toughness. Ferritic-martensitic steels are embrittled by the irradiation, and show the lowest toughness at room temperature.

    Keywords:

    fracture toughness, austenitic stainless steels, disk compact, ferritic stainless steels, first wall/blanket structure, embrittlement, tearing modulus


    Paper ID: STP16518S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP16518S


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