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

Soukhanovskii, V. A.

doi:10.1088/1361-6587/aa6959

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

Journal Article · Fri Apr 28 00:00:00 EDT 2017 · Plasma Physics and Controlled Fusion

DOI:https://doi.org/10.1088/1361-6587/aa6959· OSTI ID:1357373

Soukhanovskii, V. A. ^[1]

Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

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). As a result, this paper reviews experiments and modeling in the area of radiative detachment in the advanced magnetic divertor configurations.

View Accepted Manuscript (DOE)

Research Organization:: Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)

Sponsoring Organization:: USDOE

Grant/Contract Number:: AC52-07NA27344

OSTI ID:: 1357373

Alternate ID(s):: OSTI ID: 22718114

Report Number(s):: LLNL-JRNL--715887-DRAFT

Journal Information:: Plasma Physics and Controlled Fusion, Journal Name: Plasma Physics and Controlled Fusion Journal Issue: 6 Vol. 59; ISSN 0741-3335

Publisher:: IOP ScienceCopyright Statement

Country of Publication:: United States

Language:: English

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