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    Crack Growth Behavior of Candidate Waste Container Materials in Simulated Underground Water

    Published: Jan 1994

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    Fracture-mechanics crack growth tests were conducted on 25.4-mm-thick compact tension specimens of Types 304L and 316L stainless steel and Incoloy 825 at 93°C and 1 atmosphere of pressure in simulated J-13 well water, which is representative of the groundwater at the Yucca Mountain site in Nevada that is proposed for a high-level nuclear waste repository. Crack growth rates were measured under various load conditions: load ratios of 0.2–1.0, frequencies of 2 × 10@4-1 Hz, rise times of 1–5000 s, and peak stress intensities of 25–40 MPa˙m1/2. The measured crack growth rates are bounded by the predicted rates from the current ASME Section XI correlation for fatigue crack growth rates of austenitic stainless steel in air. Environmentally accelerated crack growth was not evident in any of the three materials under the test conditions investigated.


    crack growth, nuclear waste, waste container, metallic canister, stress corrosion cracking, corrosion fatigue

    Author Information:

    Park, JY
    Metallurgist, Argonne National Laboratory, Argonne, IL

    Shack, WJ
    Associate Director, Argonne National Laboratory, Argonne, Illinois

    Diercks, DR
    Section Manager, Argonne National Laboratory, Argonne, Illinois

    Committee/Subcommittee: G01.08

    DOI: 10.1520/STP24883S