About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
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Symposium
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Nanostructured Materials in Extreme Environments
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Presentation Title |
Study of the Microstructural Evolution of Ultrafine-grained Austenitic Stainless Steel Irradiated by Neutrons by Atom Probe Tomography and Transmission Electron Microscopy |
Author(s) |
Frederic Habiyaremye, Bertrand Radiguet, Auriane Etienne , Solène Rouland , Xavier Sauvage, Benoit Tanguy, Joël Malaplate, Christophe Domain, Remy Bonzom , Nariman Enikeev, Marina Abramova |
On-Site Speaker (Planned) |
Frederic Habiyaremye |
Abstract Scope |
Austenitic stainless steels (ASS) used as a structural material for pressurized water reactors' internal structures suffer from radiation-induced microstructural evolutions that may lead to component degradation and dimensional change. One approach to improving the irradiation resistance is to increase the number of point defect sinks, e.g., grain boundaries. Ultrafine-grained (UFG) ASS have been suggested for this purpose because they have a large density of grain boundaries. This study investigates microstructure under irradiation of a 316 UFG ASS processed by equal channel angular pressing at 400 and 500°C. Neutron irradiation was performed at CEA Saclay (France) in OSIRIS experimental reactor with neutron doses of 3.9 and 11.6 displacements per atom pa at 350°C. Microstructures are examined with atom probe tomography and transmission electron microscopy. The results are compared to the current 316L ASS reported in the literature to assess the potential application of this alloy for the Gen. II and IV nuclear reactors. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Characterization, Mechanical Properties |