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Crack Initiation of Alloy 600 in PWR Water

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Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors

Part of the book series: The Minerals, Metals & Materials Series ((MMMS))

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Abstract

Crack initiation has often been measured using simple, unmonitored tests such as bolt-loaded U bends, where the time to initiation is only estimated by occasional interruption, and the stress drops by ~12% from the change in modulus along with stress relaxation, which can be substantial in some materials and heats. The objective of this study was to develop and demonstrate improved techniques using actively loaded tensile specimens and continuous on-line monitoring of crack development using reversing DC potential drop. To complement the crack initiation data, the crack growth response of the heats and conditions was also evaluated.

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Author information

Authors and Affiliations

  1. Andresen Consulting, 12204 Wildwood Park Place, Bakersfield, CA, 93311, USA

    Peter Andresen

  2. Electric Power Research Institute, 3412 Hillview Ave, Palo Alto, CA, 94304, USA

    Peter Chou

Authors
  1. Peter Andresen
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  2. Peter Chou
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Corresponding author

Correspondence to Peter Andresen .

Editor information

Editors and Affiliations

  1. Idaho National Laboratory, Idaho Falls, ID, USA

    John H. Jackson

  2. Naval Nuclear Laboratory, Pittsburgh, PA, USA

    Denise Paraventi

  3. Chalk River Laboratories, Canadian Nuclear Laboratories, Chalk River, ON, Canada

    Michael Wright

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© 2019 The Minerals, Metals & Materials Society

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Andresen, P., Chou, P. (2019). Crack Initiation of Alloy 600 in PWR Water. In: Jackson, J., Paraventi, D., Wright, M. (eds) Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The Minerals, Metals & Materials Series. Springer, Cham. https://doi.org/10.1007/978-3-030-04639-2_8

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