COMPASS-U plasma-facing components: Towards a full W first wall coverage

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F25%3A00617644" target="_blank" >RIV/61389021:_____/25:00617644 - isvavai.cz</a>

Výsledek na webu

<a href="https://www.sciencedirect.com/science/article/pii/S0920379625000195?via%3Dihub" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0920379625000195?via%3Dihub</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.fusengdes.2025.114815" target="_blank" >10.1016/j.fusengdes.2025.114815</a>

Jazyk výsledku

angličtina

Název v původním jazyce

COMPASS-U plasma-facing components: Towards a full W first wall coverage

Popis výsledku v původním jazyce

This paper describes the plasma-facing components of tokamak COMPASS-U and how a 100 % tungsten coverage of plasma-wall interaction areas is achieved with passively cooled, bulk tungsten tiles in high heat flux regions and W-coated Inconel 718 tiles elsewhere. The choice of Inconel 718 was motivated by the future foreseen plasma operation up to 500 °C as Inconel 718 still keeps high mechanical properties up to 700 °C. In order to prevent the physical sputtering of the different elements that compose this Ni-based superalloy, a thin tungsten coating is applied by physical vapor deposition. COMPASS-U plasma-facing components consist of 1) tungsten tiles: in a closed divertor at the bottom of the machine and on 8 inner & 2 outer guard limiters to start/end plasma discharges (inner) and to cope with runaway electrons (inner & outer), and 2) W-coated tiles: on the inner wall (the tiles are slightly recessed between the inner guard limiters and cover the entire central column), on 8 discrete outer wall limiters, on the two in-vessel stabilizing coils, and finally on the temporary initial open divertor located at the top of the vacuum vessel.

Název v anglickém jazyce

COMPASS-U plasma-facing components: Towards a full W first wall coverage

Popis výsledku anglicky

This paper describes the plasma-facing components of tokamak COMPASS-U and how a 100 % tungsten coverage of plasma-wall interaction areas is achieved with passively cooled, bulk tungsten tiles in high heat flux regions and W-coated Inconel 718 tiles elsewhere. The choice of Inconel 718 was motivated by the future foreseen plasma operation up to 500 °C as Inconel 718 still keeps high mechanical properties up to 700 °C. In order to prevent the physical sputtering of the different elements that compose this Ni-based superalloy, a thin tungsten coating is applied by physical vapor deposition. COMPASS-U plasma-facing components consist of 1) tungsten tiles: in a closed divertor at the bottom of the machine and on 8 inner & 2 outer guard limiters to start/end plasma discharges (inner) and to cope with runaway electrons (inner & outer), and 2) W-coated tiles: on the inner wall (the tiles are slightly recessed between the inner guard limiters and cover the entire central column), on 8 discrete outer wall limiters, on the two in-vessel stabilizing coils, and finally on the temporary initial open divertor located at the top of the vacuum vessel.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

10304 - Nuclear physics

Projekt

Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2025

Kód důvěrnosti údajů

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

Název periodika

Fusion Engineering and Design

ISSN

0920-3796

e-ISSN

1873-7196

Svazek periodika

211

Číslo periodika v rámci svazku

February

Stát vydavatele periodika

NL - Nizozemsko

Počet stran výsledku

7

Strana od-do

114815

Kód UT WoS článku

001421177700001

EID výsledku v databázi Scopus

2-s2.0-85215848220