| Autor: |
S. Zamperini, T. Abrams, J. Nichols, E. Unterberg, A. Lasa, P. Stangeby, S. Bringuier, D. Rudakov, J.D. Elder |
| Jazyk: |
angličtina |
| Rok vydání: |
2023 |
| Předmět: |
|
| Zdroj: |
Nuclear Materials and Energy, Vol 37, Iss , Pp 101535- (2023) |
| Druh dokumentu: |
article |
| ISSN: |
2352-1791 |
| DOI: |
10.1016/j.nme.2023.101535 |
| Popis: |
Silicon carbide (SiC) is a promising material for use in a fusion reactor due to its low hydrogenic diffusivity, high temperature strength and resilience under neutron irradiation [1,2]. To assess SiC as a main wall material in DIII-D, simulations with TRIM.SP and DIVIMP are performed on a well-diagnosed L-mode discharge. The effective charge, Zeff, across the separatrix is used as a figure of merit in comparing SiC to the current graphite walls. It is found that SiC is expected to reduce Zeff, potentially by as much as ∼50 %. It is discussed how SiC may be expected to “self-condition” and create wall conditions similar to siliconization, further lowering Zeff due to efficient oxygen gettering. The potential benefits are reviewed and a path towards SiC walls in DIII-D is presented. |
| Databáze: |
Directory of Open Access Journals |
| Externí odkaz: |
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