Experimental studies of the snowflake divertor in TCV

Abstract

To address the risk that, in a fusion reactor, the conventional single-null divertor (SND) configuration may not be able to handle the power exhaust, alternative divertor configurations, such as the Snowflake divertor (SFD), are investigated in TCV. The expected benefits of the SFD-minus in terms of power load and peak heat flux are discussed and compared to experimental measurements. In addition, key results obtained during the last years are summarized.

Metadata

Item Type:	Article
Authors/Creators:	Labit, B. Canal, G. P. Christen, N. Duval, B. P. Lipschultz, B. https://orcid.org/0000-0001-5968-3684 Lunt, T. Nespoli, F. Reimerdes, H. Sheikh, U. Theiler, C. Tsui, C. K. Verhaegh, K. (khav500@york.ac.uk) Vijvers, W. A J (wv511@york.ac.uk)
Copyright, Publisher and Additional Information:	© 2017 Published by Elsevier Ltd. This is an author-produced version of the published paper. Uploaded in accordance with the publisher’s self-archiving policy
Keywords:	Detachment,Heat load mitigation,Snowflake divertor,Tokamaks
Dates:	Published (online): 27 March 2017 Accepted: 15 July 2016
Institution:	The University of York
Academic Units:	The University of York > Faculty of Sciences (York) > Physics (York)
Depositing User:	Pure (York)
Date Deposited:	07 Jun 2017 09:45
Last Modified:	16 Oct 2024 13:49
Published Version:	https://doi.org/10.1016/j.nme.2017.03.013
Status:	Published online
Refereed:	Yes
Identification Number:	10.1016/j.nme.2017.03.013
Related URLs:	http://www.scopus.com/inward/record.url?...
Open Archives Initiative ID (OAI ID):	oai:eprints.whiterose.ac.uk:117450

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Experimental studies of the snowflake divertor in TCV

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