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Effect Of Dissolved Oxygen On The SCC Susceptibility And Oxidation Of Cold-Worked 316L SS In PWR Primary Water

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Austenitic stainless steels (SS), such as 304L and 316L alloys, are largely used for structural components in nuclear power plants due to their good corrosion resistance, especially under high temperatures and aqueous environments. However, operational experience on the primary circuit of pressurized water reactors (PWRs) has shown an increasing number of cases of stress corrosion cracking (SCC) on austenitic stainless steels components after long-term exposure.

Product Number: ED22-17254-SG
Author: Thalita De Paula, Cécilie Duhamel, Catherine Guerre, Jérôme Crépin, Ian De Curières, Frédéric Datcharry, Marc Maisonneuve
Publication Date: 2022
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Slow strain rate tensile tests (SSRT) and oxidation tests were performed on a 316L stainless steel in Pressurized Water Reactors (PWR) primary water. The tests were performed under transient conditions (hydrogenated-oxygenated water cycling). The present results indicate stress corrosion cracking (SCC) susceptibility dependence of SSRT samples on cumulated time exposure to hydrogenated water. After short-time exposure under hydrogenated conditions, most of the crack-like defects are shorter than 2 μm and crack mean depth is around 5 μm. In contrast, after long-time exposure, most SCC crack-like defects are longer than 2 μm and the crack mean depth increases linearly with the cumulated time spent under hydrogenated conditions.

Slow strain rate tensile tests (SSRT) and oxidation tests were performed on a 316L stainless steel in Pressurized Water Reactors (PWR) primary water. The tests were performed under transient conditions (hydrogenated-oxygenated water cycling). The present results indicate stress corrosion cracking (SCC) susceptibility dependence of SSRT samples on cumulated time exposure to hydrogenated water. After short-time exposure under hydrogenated conditions, most of the crack-like defects are shorter than 2 μm and crack mean depth is around 5 μm. In contrast, after long-time exposure, most SCC crack-like defects are longer than 2 μm and the crack mean depth increases linearly with the cumulated time spent under hydrogenated conditions.

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