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Comparative Study on Short Time Oxidation of Un-Irradiated and Protons Pre-Irradiated 316L Stainless Steel in Simulated 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

Achieving a better understanding of the Irradiation Assisted Stress Corrosion Cracking resistance is one of the issues to improve the durability of Pressurized Water Reactors. To do so, assessing the interaction of irradiation defects with oxidation of internal vessel bolts, made of 316L alloy, is crucial. In this work we studied the effect of protons pre-irradiations at 1 dpa on the very first steps of oxidation (1 min < t < 24 h) in simulated PWR environment. The morphology of the oxide layer was investigated using optical microscopy and Scanning Electron Microscopy. The oxidation kinetics for short term oxidation is discussed based on the obtained results. It was observed that crystallographic orientation has an effect on the oxidation process. The level of cold-work and the presence of precipitates were taken into account and both seemed to accelerate the oxidation kinetic. Finally, irradiation also tended to speed-up the oxidation phenomenon.

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Acknowledgements

The authors would like to thank O. Wendling, T. Sauvage, A. Bellamy and P. Desgardin for setting up the irradiation experiment and carrying out the irradiations and, T. Girard (EDF R&D) for conducting the oxidation tests. The authors would also like to acknowledge M. Mahé (EDF R&D) for the EDXS analysis of the precipitates.

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Authors and Affiliations

  1. EDF R&D, EDF Lab Les Renardières—MMC, Avenue Des Renardières—Ecuelles, 77818, Moret Sur Loing, France

    M. Boisson, L. Legras & F. Carrette

  2. CNRS, CEMHTI UPR3079, Univ. Orléans, F-45071, Orléans, France

    O. Wendling, T. Sauvage, A. Bellamy & P. Desgardin

  3. CIRIMAT, Université de Toulouse, CNRS, INPT, UPS, ENSIACET, 4 Allée Emile Monso BP 44362, 31030, Toulouse Cedex 4, France

    M. Boisson, L. Laffont & E. Andrieu

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  1. M. Boisson
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  2. L. Legras
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  3. F. Carrette
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  4. O. Wendling
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  5. T. Sauvage
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  7. P. Desgardin
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  8. L. Laffont
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  9. E. Andrieu
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Corresponding author

Correspondence to M. Boisson .

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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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Boisson, M. et al. (2019). Comparative Study on Short Time Oxidation of Un-Irradiated and Protons Pre-Irradiated 316L Stainless Steel in Simulated 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_142

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