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Study of the interactions between hydrogen and irradiation-induced defects in 316L stainless steel

Abstract : In a Pressurized Water Reactors (PWR) core, the primary medium combined with neutron irradiation may promote IASCC (Irradiation Assisted Stress Corrosion Cracking), which may lead to premature failure of stainless steel (SS) internal components.During the oxidation process of SS occurring in simulated PWR primary water, it was shown that non negligible amounts of hydrogen were incorporated and trapped in the alloy. Neutron-irradiation of this material, increasing the number of defects (vacancies, interstitials, dislocation loops) that may act as trap sites for hydrogen, favors hydrogen accumulation in the alloy. This synergy could be a key parameter in the IASCC mechanisms.The objective of this study is to identify, characterize and understand the interactions between hydrogen and irradiation-induced defects in austenitic SS. For this purpose, a316L SS with the least defects as possible is compared with ones whose defects are created by different ion implantation experiments. After the characterization of each ones by Transmission Electron Microscopy (TEM), hydrogen uptake of the samples is promoted either by room temperature cathodic charging or during corrosion experiments in PWR primary conditions. Then hydrogen distribution and trapping is characterized by GD-OES (Glow discharge Optical Emission Spectroscopy) and TDS (Thermal Desorption Spectroscopy).The first results on the role of implantation defects on hydrogen localization and trapping will be presented.
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Submitted on : Thursday, January 16, 2020 - 1:42:52 PM
Last modification on : Wednesday, October 14, 2020 - 3:52:48 AM

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  • HAL Id : cea-02442340, version 1

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A-C. Bach, J. Crepin, C. Duhamel, F. Martin, S. Perrin. Study of the interactions between hydrogen and irradiation-induced defects in 316L stainless steel. Eurocorr 2016, Sep 2016, Montpellier, France. ⟨cea-02442340⟩

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