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15–19 Jul 2024
Metsätalo, University of Helsinki, Finland
Europe/Vienna timezone
The Decennial IAEA Technical Meeting on Atomic, Molecular and Plasma-Material Interaction Data for Fusion Science and Technology

Unveiling Surface Chemistry and Hardening Mechanisms in Fusion and Nuclear Materials

16 Jul 2024, 16:10
1h 30m
Metsätalo, 3rd floor, University of Helsinki

Metsätalo, 3rd floor, University of Helsinki

Unioninkatu 40 00170 Helsinki Finland

Speaker

Dr Francisco Javier Dominguez Gutierrez (National Centre for Nuclear Research)

Description

This work presents a combined theoretical and experimental approach to understand the complex surface phenomena occurring in fusion and nuclear materials.
Fusion Materials: We investigate the interaction of low-Z (lithium and boron) coatings with carbon under extreme fusion plasma conditions. A multi-scale approach using computational modeling, real-time plasma diagnostics, and ex-vessel in-situ experiments unravels the evolving characteristics of these surfaces. We explore the effects of these coatings on deuterium retention and chemical sputtering, with a focus on the critical role of oxygen in driving the surface chemistry during hydrogen irradiation. These findings can hold significant implications for fusion plasma confinement behavior. Additionally, computational studies expand beyond limitations of empirical methods, paving the way for a strategic approach integrating advanced modeling tools with in-vessel and ex-vessel diagnostics.

Nuclear Materials: We analyze the hardening behavior of irradiated and pristine BCC and FCC alloys for nuclear applications. Nanoindentation testing reveals significant hardening effects by both experiments and computational modelling. The observed qualitative agreement between experimental load-displacement data and MD simulations suggests sluggish dislocation diffusion, reduced defect sizes, and tetrahedral stacking fault nucleation as key strengthening factors. Notably, experimental observations point towards the nucleation of interstitial-type prismatic dislocation loops during loading, shedding light on the material's hardening mechanisms. In FCC materials specifically, these loops interact to form pyramidal stacking faults, primarily driven by ⅓⟨100⟩ Hirth dislocation lines. The co-existence of both defect types observed in the plastic deformation zone further supports the combined experimental and computational approach. Reported mechanical data, experimental and numerical, are validated by microstructural SEM and TEM investigations. Finally, we discuss the advantages and limitations of conventional interatomic potentials and machine-learned models in simulating nanoindentation tests.

This work provides valuable insights into surface chemistry and hardening mechanisms in both fusion and nuclear materials, paving the way for advancements in material design and optimization for extreme environments.

Primary author

Dr Francisco Javier Dominguez Gutierrez (National Centre for Nuclear Research)

Co-authors

Damian Kalita (National Centre for Nuclear Research) Katarzyna Mulewska (National Centre for Nuclear Research) Dr Lukasz Kurpaska (National Centre for Nuclear Research) Marie Landeiro Dos-Reis (La Rochelle University) Dr Mikko Alava (National Centre for Nuclear Research)

Presentation materials