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Island Divertor: Difference between revisions
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The Island Divertor is a concept in magnetic confinement fusion devices that utilizes inherent low-order magnetic islands to manage power and particle exhaust. Developed for advanced low-shear stellarators in the Wendelstein-7 family, the island divertor was first tested on W7-AS before its shutdown in 2002<ref>[[doi:10.1088/0029-5515/46/8/006|Y. Feng et al ., Nucl. Fusion '''46''' (2006) 807]]</ref>. The concept has since been investigated in more detail and at a larger scale in Wendelstein 7-X (W7-X). | The Island Divertor is a concept in magnetic confinement fusion devices that utilizes inherent low-order [[magnetic island|magnetic islands]] to manage power and particle exhaust. Developed for advanced low-shear [[stellarator|stellarators]] in the Wendelstein-7 family, the island divertor was first tested on W7-AS before its shutdown in 2002<ref>[[doi:10.1088/0029-5515/46/8/006|Y. Feng et al ., Nucl. Fusion '''46''' (2006) 807]]</ref>. The concept has since been investigated in more detail and at a larger scale in Wendelstein 7-X (W7-X). | ||
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. | ||