About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
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Symposium
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Mechanical Behavior of Nuclear Reactor Materials and Components III
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Presentation Title |
Estimating the Strengthening Parameters for Irradiated Alloys using Atomic Scale |
Author(s) |
Osetsky Yury, German Samolyuk |
On-Site Speaker (Planned) |
Osetsky Yury |
Abstract Scope |
Models based on the dispersed barrier hardening (DBH) approach are often used for interpreting experimental results and estimating the mechanical response of irradiated materials. However, the accuracy of DBH models is rather low due to weak physical approaches and phenomenological fitting in estimating the obstacle strength parameter. We suggest a new approach that utilizes the accumulated over decades results of atomic scale modeling of dislocation-obstacle interactions, much of which is directly related to radiation induced defects. In this work, we developed a simple approach that combines early parametric continuum modeling with current atomic scale dislocation dynamics. This approach allows estimating the size and temperature dependent values of obstacle strength parameters, using the available atomistic modeling data. Examples are presented for cases in two materials of practical significance e.g. ferritic and tungsten-rhenium alloys. The implication of these results to the understanding of experimental observations is discussed.
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Proceedings Inclusion? |
Planned: |
Keywords |
Mechanical Properties, Modeling and Simulation, Nuclear Materials |