Neutral density measurements in doublet III

The present vision for a plasma-material interface in the tokamak is an axisymmetric poloidal magnetic X-point divertor. Four tasks are accomplished by the standard poloidal X-point divertor: plasma power exhaust; particle control (D/T and He pumping); reduction of impurity production (source); and impurity screening by the divertor scrape-off layer. A low-temperature, low heat flux divertor operating regime called radiative detachment is viewed as the main option that addresses these tasks for present and future tokamaks. Advanced magnetic divertor configuration has the capability to modify divertor parallel and cross-field transport, radiative and dissipative losses, and detachment front stability. Advanced magnetic divertor configurations are divided into four categories based on their salient qualitative features: (1) multiple standard X-point divertors; (2) divertors with higher order nulls; (3) divertors with multiple X-points; and (4) long poloidal leg divertors (and also with multiple X-points). This paper reviews experiments and modeling in the area of radiative detachment in the advanced magnetic divertor configurations.

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Divertor Physics and Concept Development on DIII-D and Doublet-III Tokamaks

Mahdavi

Allen

Fenstermacher

et al. 2005

Fusion Science and Technology

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Neutral density measurements in doublet III

Cited by 3 publications

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Experimental evidence of increased electron temperature, plasma potential, and ion energy near an ICRF antenna Faraday shield

Experimental evidence of increased electron temperature, plasma potential, and ion energy near an ICRF antenna Faraday shield

A review of radiative detachment studies in tokamak advanced magnetic divertor configurations

Divertor Physics and Concept Development on DIII-D and Doublet-III Tokamaks

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