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Island Divertor: Difference between revisions
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One major challenge magnetic confinement fusion devices face is managing power and particle exhaust. In future reactors, hundreds of MWs of power will stream out from the confined plasma region (core) and must be dissipated before reaching the plasma-facing components (PFCs). Excessive heat and erosion can lead to short lifetimes of the PFCs, as well as the release of impurities and subsequent contamination of the confined plasma. | One major challenge magnetic confinement fusion devices face is managing power and particle exhaust. In future reactors, hundreds of MWs of power will stream out from the confined plasma region (core) and must be dissipated before reaching the plasma-facing components (PFCs). Excessive heat and erosion can lead to short lifetimes of the PFCs, as well as the release of impurities and subsequent contamination of the confined plasma. | ||
[[Divertor|Divertors]] are dedicated plasma-wall interaction zones where particles and heat stream to, moving parallel to the open magnetic field lines in the scrape-off layer (SOL). However, the fast parallel heat transport leads to localized heat deposition on the targets. In stellarators, several edge topologies have been proposed and used to form a divertor for particle and heat exhaust. The island divertor is one such concept, using intrinsic magnetic islands in the SOL to set up a divertor volume. | [[Divertor|Divertors]] are dedicated plasma-wall interaction zones where particles and heat stream to, moving parallel to the open magnetic field lines in the scrape-off layer (SOL). However, the fast parallel heat transport leads to localized heat deposition on the targets. In stellarators, several edge topologies have been proposed and used to form a divertor for particle and heat exhaust (e.g., helical divertor, non-resonant divertor).<ref>http://www.jspf.or.jp/jspf_annual2018/JSPF35/pdf/S8-4.pdf</ref> The island divertor is one such concept, using intrinsic magnetic islands in the SOL to set up a divertor volume. | ||
The first W7-X island divertor experiments and 3D modeling studies with [[EMC3-EIRENE|EMC3-EIRENE]] have found a strong dependence of the divertor heat fluxes on the magnetic configurations and island geometry. Local heat load profiles showed offsets and varying peak fluxes, complicating the matching between experiments and 3D modeling<ref>[[doi:10.1016/j.nme.2019.01.006|F. Effenberg, et al, Nucl. Mater. Energy '''18''' (2019) 262-267]]</ref><ref>[[doi:10.1088/1741-4326/ab18d1|J.D. Lore et al, Nucl. Fusion '''59''' (2019) 066041]]</ref>. | The first W7-X island divertor experiments and 3D modeling studies with [[EMC3-EIRENE|EMC3-EIRENE]] have found a strong dependence of the divertor heat fluxes on the magnetic configurations and island geometry. Local heat load profiles showed offsets and varying peak fluxes, complicating the matching between experiments and 3D modeling<ref>[[doi:10.1016/j.nme.2019.01.006|F. Effenberg, et al, Nucl. Mater. Energy '''18''' (2019) 262-267]]</ref><ref>[[doi:10.1088/1741-4326/ab18d1|J.D. Lore et al, Nucl. Fusion '''59''' (2019) 066041]]</ref>. | ||