A review of radiative detachment studies in tokamak advanced magnetic divertor configurations
Abstract
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.
- Authors:
-
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Publication Date:
- Research Org.:
- Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1357373
- Report Number(s):
- LLNL-JRNL-715887-DRAFT
Journal ID: ISSN 0741-3335
- Grant/Contract Number:
- AC52-07NA27344
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Plasma Physics and Controlled Fusion
- Additional Journal Information:
- Journal Volume: 59; Journal Issue: 6; Journal ID: ISSN 0741-3335
- Publisher:
- IOP Science
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION
Citation Formats
Soukhanovskii, V. A. A review of radiative detachment studies in tokamak advanced magnetic divertor configurations. United States: N. p., 2017.
Web. doi:10.1088/1361-6587/aa6959.
Soukhanovskii, V. A. A review of radiative detachment studies in tokamak advanced magnetic divertor configurations. United States. https://doi.org/10.1088/1361-6587/aa6959
Soukhanovskii, V. A. Fri .
"A review of radiative detachment studies in tokamak advanced magnetic divertor configurations". United States. https://doi.org/10.1088/1361-6587/aa6959. https://www.osti.gov/servlets/purl/1357373.
@article{osti_1357373,
title = {A review of radiative detachment studies in tokamak advanced magnetic divertor configurations},
author = {Soukhanovskii, V. A.},
abstractNote = {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.},
doi = {10.1088/1361-6587/aa6959},
journal = {Plasma Physics and Controlled Fusion},
number = 6,
volume = 59,
place = {United States},
year = {Fri Apr 28 00:00:00 EDT 2017},
month = {Fri Apr 28 00:00:00 EDT 2017}
}
Web of Science
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Application of the radiating divertor approach to innovative tokamak divertor concepts
journal, August 2015
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journal, September 1978
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journal, March 2001
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Ion drifts in a snowflake divertor
journal, January 2010
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Investigation of Advanced Divertor Magnetic Configuration for DEMO Tokamak Reactor
journal, January 2013
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The Stellarator Concept
journal, January 1981
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Benchmarking of a 1D Scrape-off layer code SOLF1D with SOLPS and its use in modelling long-legged divertors
text, January 2013
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- arXiv
MAST-Upgrade Divertor Facility and Assessing Performance of Long-Legged Divertors
text, January 2013
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- arXiv
Magnetic Geometry and Physics of Advanced Divertors: The X-Divertor and the Snowflake
text, January 2013
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- arXiv
Works referencing / citing this record:
Developing physics basis for the snowflake divertor in the DIII-D tokamak
journal, February 2018
- Soukhanovskii, V. A.; Allen, S. L.; Fenstermacher, M. E.
- Nuclear Fusion, Vol. 58, Issue 3
Performance assessment of long-legged tightly-baffled divertor geometries in the ARC reactor concept
journal, September 2019
- Wigram, M. R. K.; LaBombard, B.; Umansky, M. V.
- Nuclear Fusion, Vol. 59, Issue 10
SOLPS simulations with electron kinetic effects
journal, January 2019
- Zhao, Menglong; Chankin, Alex; Coster, David
- Plasma Physics and Controlled Fusion, Vol. 61, Issue 2
Self-consistent simulation of supersonic plasma flows in advanced divertors
journal, June 2019
- Togo, Satoshi; Takizuka, Tomonori; Reiser, Dirk
- Nuclear Fusion, Vol. 59, Issue 7