Divertor heat load study in COMPASS using IR thermography and divertor probes.

Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F17%3A00481896" target="_blank" >RIV/61389021:_____/17:00481896 - isvavai.cz</a>
Result on the web
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DOI - Digital Object Identifier
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Result language
angličtina
Original language name
Divertor heat load study in COMPASS using IR thermography and divertor probes.
Original language description
Heat flux magnitude and distribution over first wall and plasma facing components is a key issue for next step fusion devices in order to avoid damage of inner vessel components and secure reliable operation. Radial profiles of parallel heatnflux in present tokamaks and their scaling towards next step devices are thus of special interest. Heat flux distribution in the inner and outer divertor region was studied in the COMPASS tokamak by the means of fast infrared (IR) thermography and divertor probe arrays.
Czech name
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Czech description
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Project
Result was created during the realization of more than one project. More information in the Projects tab.
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Publication year
2017
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Article name in the collection
EPS 2017: 44th European Physical Society Conference on Plasma Physics
ISBN
979-10-96389-07
ISSN
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e-ISSN
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Number of pages
4
Pages from-to
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Publisher name
European Physical Society
Place of publication
Mulhouse
Event location
Belfast
Event date
Jun 26, 2017
Type of event by nationality
EUR - Evropská akce
UT code for WoS article
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