COMPASS-U Plasma-Facing Components: Towards a Full Tungsten First Wall Coverage

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F24%3A00617277" target="_blank" >RIV/61389021:_____/24:00617277 - isvavai.cz</a>

Výsledek na webu

<a href="https://soft2024.eu/wp-content/uploads/2024/09/SOFT-2024_Book-of-Abstracts_20-09-2024.pdf" target="_blank" >https://soft2024.eu/wp-content/uploads/2024/09/SOFT-2024_Book-of-Abstracts_20-09-2024.pdf</a>

DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

COMPASS-U Plasma-Facing Components: Towards a Full Tungsten First Wall Coverage

Popis výsledku v původním jazyce

COMPASS-U is designed to be the first tokamak to start its operation in a fully metallic environment (no carbon) with high magnetic field (5 T) and high plasma current (2 MA). The expected large energy flux densities (<80 MW/m2 and λqomp ~1 mm) and neutral pressure (~5 Pa) in the close divertor, combined to the possibility to operate at 500oC, make it relevant, in some research areas, to next step devices such as ITER and DEMO. Part of its scientific program is focused on the effect of tungsten sputtering on plasma discharges start-up and performances, tungsten erosion and transport in the SOL & pedestal, influence of wall temperature on recycling and deuterium retention, and plasma operation/performance with full recycling walls. A full tungsten coverage of the first wall is an asset for the fusion community especially with ITER considering to replace Be panels by W ones

Název v anglickém jazyce

COMPASS-U Plasma-Facing Components: Towards a Full Tungsten First Wall Coverage

Popis výsledku anglicky

COMPASS-U is designed to be the first tokamak to start its operation in a fully metallic environment (no carbon) with high magnetic field (5 T) and high plasma current (2 MA). The expected large energy flux densities (<80 MW/m2 and λqomp ~1 mm) and neutral pressure (~5 Pa) in the close divertor, combined to the possibility to operate at 500oC, make it relevant, in some research areas, to next step devices such as ITER and DEMO. Part of its scientific program is focused on the effect of tungsten sputtering on plasma discharges start-up and performances, tungsten erosion and transport in the SOL & pedestal, influence of wall temperature on recycling and deuterium retention, and plasma operation/performance with full recycling walls. A full tungsten coverage of the first wall is an asset for the fusion community especially with ITER considering to replace Be panels by W ones

Druh

O - Ostatní výsledky

CEP obor

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OECD FORD obor

20501 - Materials engineering

Projekt

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Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2024

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů