About this Abstract |
Meeting |
2022 TMS Annual Meeting & Exhibition
|
Symposium
|
Materials Systems for the Future of Fusion Energy
|
Presentation Title |
Deuterium Trapping and Release from Irradiation-induced Voids in Tungsten: Theory and Experimental Validation |
Author(s) |
Mikhail Zibrov, Klaus Schmid |
On-Site Speaker (Planned) |
Mikhail Zibrov |
Abstract Scope |
Since tungsten (W) plasma-facing components in fusion reactors will operate at elevated temperatures, formation of irradiation-induced voids in them is expected. Based on the diffusion theory and the kinetic theory of the interaction of D2 gas with metal surfaces, we develop a self-consistent formalism for describing deuterium trapping and release from voids in metals. This formalism has been implemented into the diffusion-trapping code TESSIM. First, we performed 3D simulations of deuterium interaction with a single void in W to elucidate the main features of trapping and release. Significant differences compared with point defects are demonstrated. We also show that the commonly used equilibrium approximations often lead to erroneous results. Then we performed simulations for a system of voids in a 1D continuum approximation and compare them with 3D simulations. Finally, we applied our model for describing experimental deuterium thermal desorption spectra from voids in self-ion irradiated W. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Modeling and Simulation, |