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Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors pp 695–708Cite as

Void Swelling Screening Criteria for Stainless Steels in PWR Systems

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

Abstract

Most of the available void swelling (VS) data are from fast reactors rather than PWRs, but there are indications that the saturation VS rate for PWR-relevant conditions is at least an order of magnitude smaller than that observed in fast reactors. In 2005, VS screening criteria (temperatures ≥320 °C (608 °F) and fluence ≥20 dpa) were calculated. Since publication of these initial screening criteria, a physics-based model has been developed for the prediction of VS in irradiated austenitic stainless steel components. Comparisons between experimental data derived from density measurements and transmission electron microscopy (TEM) characterizations suggest that the Cluster Dynamics model is capable of predicting the evolution of the irradiated microstructure under PWR conditions. The Cluster Dynamics model estimates <1.5% VS for solution-annealed or cold-worked austenitic stainless steel at temperatures below 320 °C (608 °F) and doses <20 dpa for all displacement rates. Therefore, the previous conservative screening criteria originally calculated in 2005 are retained.

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Author information

Authors and Affiliations

  1. AREVA Inc., P.O. Box 10935, Lynchburg, VA, 24506-0935, USA

    Sarah Davidsaver & Steve Fyfitch

  2. AREVA NP, Tour AREVA—BP 1851C-3 1, Place Jean Millier, 92084, Paris La Defense Cedex, France

    Daniel Brimbal

  3. Westinghouse Electric Company, 1000 Westinghouse Drive, Cranberry Township, PA, 16066, USA

    Joshua McKinley

  4. Electric Power Research Institute, 3420 Hillview Avenue, Palo Alto, CA, 94304-1395, USA

    Kyle Amberge

Authors
  1. Sarah Davidsaver
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  2. Steve Fyfitch
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  3. Daniel Brimbal
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  4. Joshua McKinley
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  5. Kyle Amberge
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Corresponding author

Correspondence to Sarah Davidsaver .

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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Davidsaver, S., Fyfitch, S., Brimbal, D., McKinley, J., Amberge, K. (2019). Void Swelling Screening Criteria for Stainless Steels in PWR Systems. 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_45

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