4.3 Article

Plasma detachment in divertor tokamaks

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IOP PUBLISHING LTD
DOI: 10.1088/1361-6587/aaa7a9

关键词

divertors; detachment; tokamaks; divertor heat flux; radiative divertor

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  1. US Department of Energy, Office of Science, Office of Fusion Energy Sciences, using the DIII-D National Fusion Facility, a DOE Office of Science user facility [DE-FC02-04ER54698]

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Observations of divertor plasma detachment in tokamaks are reviewed. Plasma detachment is characterized in terms of transport and dissipation of power, momentum and particle flux along the open field lines from the midplane to the divertor. Asymmetries in detachment onset and other characteristics between the inboard and outboard divertor plasmas is found to be primarily driven by plasma (E) over right arrow X (B) over right arrow drifts. The effect of divertor plate geometry and magnetic configuration on divertor detachment is summarized. Control of divertor detachment has progressed with a development of a number of diagnostics to characterize the detached state in real-time. Finally the compatibility of detached divertor operation with high performance core plasmas is examined.

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