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  4. Experimental Studies of the Snowflake Divertor in TCV
 
conference paper

Experimental Studies of the Snowflake Divertor in TCV

Labit, B
•
Canal, G P
•
Christen, N
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2017
Nuclear Materials and Energy
PSI 2016<br/>22nd Plasma Surface Interactions Conference

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. (C) 2017 Published by Elsevier Ltd. This is an open access article under the CC BY-NC-ND license. (http://creativecommons.org/licenses/by-nc-nd/4.0/)

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Type
conference paper
DOI
10.1016/j.nme.2017.03.013
Web of Science ID

WOS:000417293300166

Author(s)
Labit, B
Canal, G P
Christen, N
Duval, B P
Lipschultz, B
Lunt, T
Nespoli, F
Reimerdes, H
Sheikh, U
Theiler, C
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Date Issued

2017

Publisher

Elsevier Science Bv

Publisher place

Amsterdam

Published in
Nuclear Materials and Energy
Total of pages

5

Volume

12

Start page

1015

End page

1019

Subjects

Tokamaks

•

Snowflake divertor

•

Detachment

•

Heat load mitigation

URL

URL

http://www.psi2016.enea.it

URL

https://crpplocal.epfl.ch/pinboard/papers/164113303.pdf
Editorial or Peer reviewed

REVIEWED

Written at

EPFL

EPFL units
SPC  
Event nameEvent placeEvent date
PSI 2016<br/>22nd Plasma Surface Interactions Conference

Roma, Italia

30 May - 03 June 2016

Available on Infoscience
March 10, 2017
Use this identifier to reference this record
https://infoscience.epfl.ch/handle/20.500.14299/135164
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