Simulated temperature of a tungsten spot facing large plasma heat loads
In fusion devices like ITER, plasma-wall interactions are a significant concern due to the high heat fluxes, often tens of MW/m 2 , impacting the first wall. These intense heat fluxes can lead to the formation of hot spots on components facing the plasma, such as tungsten, used in divertor plates and antennas. This results in material erosion and plasma core contamination. Our study investigates the thermal behavior of tungsten surfaces under these conditions using fluid modeling and Particle-In-Cell (PIC) simulations. We examine the effects of thermionic electron emission on the sheath potential and heat transmission. The simulations reveal that thermionic emission can decrease the sheath voltage, increasing the surface temperature due to enhanced heat flux due to electrons. Additionally, we explore how the ratio between the spot size ( S ) and the surrounding surface length ( L y ) influences the surface temperature. We find that a higher L y / S ratio allows the surface to reach higher temperatures before the system enters the space-charge-limited regime, where thermionic current is maximized and considerably larger than the case where the entire surface is emissive ( L y = S ). • Investigation of thermal behavior of tungsten surfaces under high plasma heat loads using fluid modeling and Particle-In-Cell (PIC) simulations. • Thermionic emission decreases sheath voltage, enhancing surface temperature due to increased heat flux. • Ratio between spot size (S) and surrounding surface length (Ly) affects directly surface temperature due to the return path of the electron current. • Higher Ly/S ratios allows the surface to reach higher temperatures before the system enters the space charge limited regime.
Authors
- S. Heuraux (ORCID: https://orcid.org/0000-0001-7035-4574)
- F. Brochard (ORCID: https://orcid.org/0000-0002-6578-6046)
- L. Marot (ORCID: https://orcid.org/0000-0002-1529-9362)
- P. Hiret (ORCID: https://orcid.org/0000-0002-2119-8648)
- J. Moritz (ORCID: https://orcid.org/0000-0002-4593-6270)
- Maxime Lesur (ORCID: https://orcid.org/0000-0001-9747-5616)
- E. Gravier (ORCID: https://orcid.org/0000-0002-8911-5546)
Institutions
- Centre National de la Recherche Scientifique (FR)
- University of Basel (CH)
- Institut Jean Lamour (FR)
- Université de Lorraine (FR)
Publication Details
- Journal
- Nuclear Materials and Energy
- Published
- 2024-10-08
- DOI
- https://doi.org/10.1016/j.nme.2024.101753
- Citations
- 1
- Primary Topic
- Fusion materials and technologies
- Type
- article
- Field-Weighted Citation Impact
- 0.12
Funders
- EUROfusion
- European Commission
- Agence Nationale de la Recherche