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IASCC Susceptibility of 304L Stainless Steel Irradiated in a BWR and Subjected to Post Irradiation Annealing

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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

Post-irradiation annealing (PIA) was conducted to investigate the cause of irradiation-assisted stress corrosion cracking (IASCC) . The effects of PIA on irradiation hardening , dislocation channel formation, and IASCC susceptibility were examined for a 304L stainless steel irradiated to 5.9 dpa in the Barsebäck-1 reactor (Sweden). The annealing treatments were performed at temperatures in the range 450–600 °C and times ranging from 1–20 h. Longer annealing times and higher temperatures, as represented by iron diffusion distance, resulted in a significant reduction in irradiation hardening. IASCC susceptibility was measured for the as-irradiated and two PIA conditions (500 °C: 1 h and 550 °C: 20 h) via interrupted CERT tests under simulated BWR-NWC conditions. The annealing treatments progressively reduced IASCC susceptibility (as measured by the final intergranular fracture fraction) and dislocation channel density.

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Acknowledgements

The authors would like to thank Alex Flick for assistance in operation of the CERT experiments at the Irradiated Materials Testing Laboratory and the University of Michigan. Gratitude is also extended to Maxim Gussev and the technical support staff at the Low Activity Materials Development and Analysis Laboratory at Oak Ridge National Laboratory for assistance with specimen handling and preparation. Support for this project was provided by funding from the Nuclear Energy University Programs (project number: DE-AC07-05ID14517) and under appointment to the Rickover Fellowship Program in Nuclear Engineering sponsored by Naval Reactors Division of the U.S. Department of Energy.

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Authors and Affiliations

  1. University of Michigan, 2355 Bonisteel Blvd., Ann Arbor, MI, 48109-1204, USA

    Justin R. Hesterberg, Zhijie Jiao & Gary S. Was

Authors
  1. Justin R. Hesterberg
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  2. Zhijie Jiao
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  3. Gary S. Was
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Corresponding author

Correspondence to Justin R. Hesterberg .

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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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Hesterberg, J.R., Jiao, Z., Was, G.S. (2019). IASCC Susceptibility of 304L Stainless Steel Irradiated in a BWR and Subjected to Post Irradiation Annealing. 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_150

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