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| Naji, M. |
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| Motta, Antonella |
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| Aletan, Dirar |
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| Mohamed, Tarek |
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| Ertürk, Emre |
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| Taccardi, Nicola |
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| Kononenko, Denys |
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| Petrov, R. H. | Madrid |
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| Alshaaer, Mazen | Brussels |
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| Bih, L. |
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| Casati, R. |
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| Muller, Hermance |
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| Kočí, Jan | Prague |
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| Šuljagić, Marija |
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| Kalteremidou, Kalliopi-Artemi | Brussels |
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| Azam, Siraj |
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| Ospanova, Alyiya |
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| Blanpain, Bart |
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| Ali, M. A. |
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| Popa, V. |
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| Rančić, M. |
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| Ollier, Nadège |
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| Azevedo, Nuno Monteiro |
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| Landes, Michael |
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| Rignanese, Gian-Marco |
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Martin, Frantz
CEA Saclay
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (23/23 displayed)
- 2024Hydrogen Embrittlement Characterization of 1.4614 and 1.4543 Martensitic Precipitation Hardened Stainless Steels
- 2024Experimental study of the hydrogen-microstructure interactions in a pre-strained 316L austenitic stainless steelcitations
- 2023Effect of surface nitriding on the durability of a Ti-6Al-4V alloy in high temperature pressurized liquid water
- 2022Flow Accelerated Corrosion of titanium alloys in water at 300 °C and 15 MPa
- 2022Experimental assessment of flow accelerated corrosion in nuclear components
- 2022Hydrogen transport in 17-4 PH stainless steel: Influence of the metallurgical state on hydrogen diffusion and trapping
- 2022Effect of nitriding on the corrosion of Ti64 titanium alloy in pressurized water
- 2021Revisiting the effects of low-concentration hydrogen in NiTi self-expandable stentscitations
- 2020Corrosion of titanium alloys in pressurized water at 300 °C and 15 MPa
- 2019Kinetics of hydrogen desorption from Zircaloy-4: Experimental and Modellingcitations
- 2019Hydrogen diffusion and trapping in FCC alloys: a quantitative approach based on experimental data and numerical analysis
- 2019Corrosion of titanium alloys in pressurised water at 300 °C and 350 °C
- 2019Stable isotopes used in the definition of corrosion mechanisms
- 2018Kinetics of hydrogen permeation through a Ni-base alloy membrane exposed to primary medium of pressurized water reactorscitations
- 2018Hydrogen trapping by irradiation-induced defects in 316L stainless steel
- 2017Isotopic tracing of hydrogen transport and trapping in nuclear materialscitations
- 2017Hydrogen trapping by irradiation-induced defects in 316L stainless steel
- 2016Role of grain boundaries in the diffusion of hydrogen in nickel base alloy 600:Study coupling thermal desorption mass spectroscopy with numerical simulationcitations
- 2016Role of grain boundaries in the diffusion of hydrogen in nickel base alloy 600: Study coupling thermal desorption mass spectroscopy with numerical simulationcitations
- 2016Hydrogen diffusion process in the oxides formed on Zirconium Alloys during corrosion in Pressurized Water Reactor Conditionscitations
- 2012Hydrogen Transport in 34CrMo4 Martensitic Steel: Influence of Microstructural Defects on H Diffusioncitations
- 2010A detailed TEM and SEM study of Ni-base alloys oxide scales formed in primary conditions of pressurized water reactorcitations
- 2005In situ AFM study of localised corrosion on a 304L stainless steel
Places of action
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document
Hydrogen trapping by irradiation-induced defects in 316L stainless steel
Abstract
The irradiation-induced defects in stainless steel internal components of pressurized water reactors combined with hydrogen uptake during the oxidation process could be a key parameter in the mechanism for Irradiation-Assisted Stress Corrosion Cracking (IASCC). The ultimate aim of this study is to characterize the effects of irradiation defects on hydrogen uptake during the oxidation of an austenitic stainless steel (SS) in primary water. The focus was made on the interactions between hydrogen and these defects. A heat-treated 316L SS containing a low amount of defects is compared with ion implanted samples. Both materials were characterized by Transmission Electron Microscopy (TEM). Hydrogen uptake was then promoted by cathodic charging using deuterium as isotopic tracer for hydrogen. The deuterium distribution was first characterized by SIMS (Secondary Ion Mass Spectrometry) profiles. This technique highlighted some deuterium segregation in link with the localization of implantation-induced defects, i.e. dislocation loops and cavities. Using TDS (Thermal Desorption Spectrometry) experimental results and literature data, a numerical model was used to simulate the deuterium profiles, providing diffusion and trapping/detrapping information associated with irradiation defects in the 316L SS.