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

0481896 - ÚFP 2018 RIV FR eng C - Konferenční příspěvek (zahraniční konf.)
Vondráček, Petr - Adámek, Jiří - Cavalier, Jordan - Devitre, A. - Horáček, Jan - Hron, Martin - Pánek, Radomír - Peterka, Matěj - Seidl, Jakub
Divertor heat load study in COMPASS using IR thermography and divertor probes.
EPS 2017: 44th European Physical Society Conference on Plasma Physics. Vol. 41F. Mulhouse: European Physical Society, 2017 - (Fajardo, M.; Westerhof, E.; Riconda, C.; Melzer, A.; Bret, A.; Dromey, B.), č. článku P1.120. Europhysics Conference Abstracts (ECA). ISBN 979-10-96389-07.
[EPS 2017 Conference on Plasma Physics/44./. Belfast (IE), 26.06.2017-30.06.2017]
Grant CEP: GA MŠMT(CZ) 8D15001; GA MŠMT(CZ) LM2015045; GA ČR(CZ) GA15-10723S; GA ČR(CZ) GA16-14228S
GRANT EU: European Commission(XE) 633053 - EUROfusion
Institucionální podpora: RVO:61389021
Klíčová slova: tokamak * COMPASS tokamak * infrared (IR) thermography
Obor OECD: Fluids and plasma physics (including surface physics)

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 heat
flux 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.
Trvalý link: http://hdl.handle.net/11104/0277354