Surface modifications on unirradiated and ion-irradiated tungsten after exposed to deuterium plasma at LHD divertor-leg position
In order to clarify the divertor plasma-induced tungsten (W) surface modifications as well as the irradiation defects effect, two kinds of ITER grade W were exposed to the large helical device deuterium (D) plasma at the divertor-leg position. One was the iron (Fe) ion irradiated W to produce irradi...
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| Autori principali: | , , , , , , |
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| Natura: | Artigo |
| Lingua: | Inglês |
| Pubblicazione: |
IOP Publishing
2025-01-01
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| Serie: | Nuclear Fusion |
| Soggetti: | |
| Accesso online: | https://doi.org/10.1088/1741-4326/adb862 |
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