Front face shaping of the inner wall tiles in the COMPASS Upgrade tokamak

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F23%3A00578059" target="_blank" >RIV/61389021:_____/23:00578059 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/00216208:11320/23:10467912

Výsledek na webu

<a href="https://www.sciencedirect.com/science/article/pii/S0920379623003149?via%3Dihub" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0920379623003149?via%3Dihub</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.fusengdes.2023.113731" target="_blank" >10.1016/j.fusengdes.2023.113731</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Front face shaping of the inner wall tiles in the COMPASS Upgrade tokamak

Popis výsledku v původním jazyce

The central column of the COMPASS Upgrade tokamak, where the plasma discharges will be started and shut down, is covered by a continuous first wall composed of 8 bulk tungsten guard limiters with recessed Inconel tiles in between. In diverted configurations, the plasma will be limited for a short duration (similar to 0.2 s-0.4 s) during the plasma current ramp-up and ramp-down phases but high heat fluxes due to short power decay lengths are foreseen. An adapted shaping is therefore needed to spread the heat loads over a maximum area. A novel method taking into account the different magnetic equilibria and the incident angle of the field lines was used to design a roof shape able to ensure a constant heat flux on the toroidal direction, accounting for the lambda(gnear-SOL) and lambda(gfar-SOL) Due to the diversity of plasma scenarios considered on COMPASS-U, the optimized shape of the inner wall tiles strongly differs from one scenario to another, thus a compromise has to be found among all foreseen scenarios. The tile shaping also needs to take into account possible short wave misalignments. Calculations with the 3D magnetic field line tracing code PFCFlux validates the design, confirming the constant toroidal profile of deposited heat flux for the COMPASS-U workhorse scenarios, or slightly decreasing or increasing heat flux profiles (from the center to the sides of the tile) for scenarios with smaller or higher lambda(gnear-SOL) respectively, within the expected large range (1.7 mm<lambda(gnear-SOL)<5 mm), but still providing acceptable loads. Estimated heat fluxes are in the range of 5 MW/m(2) to 35 MW/m(2) on the 8 guard limiters, receiving 70%-80% of the power deposited to the inner wall. In case of shortwave misalignments up to 0.5 mm in the radial direction, calculations show that leading edges are still protected, confirming the robustness of the design.

Název v anglickém jazyce

Front face shaping of the inner wall tiles in the COMPASS Upgrade tokamak

Popis výsledku anglicky

The central column of the COMPASS Upgrade tokamak, where the plasma discharges will be started and shut down, is covered by a continuous first wall composed of 8 bulk tungsten guard limiters with recessed Inconel tiles in between. In diverted configurations, the plasma will be limited for a short duration (similar to 0.2 s-0.4 s) during the plasma current ramp-up and ramp-down phases but high heat fluxes due to short power decay lengths are foreseen. An adapted shaping is therefore needed to spread the heat loads over a maximum area. A novel method taking into account the different magnetic equilibria and the incident angle of the field lines was used to design a roof shape able to ensure a constant heat flux on the toroidal direction, accounting for the lambda(gnear-SOL) and lambda(gfar-SOL) Due to the diversity of plasma scenarios considered on COMPASS-U, the optimized shape of the inner wall tiles strongly differs from one scenario to another, thus a compromise has to be found among all foreseen scenarios. The tile shaping also needs to take into account possible short wave misalignments. Calculations with the 3D magnetic field line tracing code PFCFlux validates the design, confirming the constant toroidal profile of deposited heat flux for the COMPASS-U workhorse scenarios, or slightly decreasing or increasing heat flux profiles (from the center to the sides of the tile) for scenarios with smaller or higher lambda(gnear-SOL) respectively, within the expected large range (1.7 mm<lambda(gnear-SOL)<5 mm), but still providing acceptable loads. Estimated heat fluxes are in the range of 5 MW/m(2) to 35 MW/m(2) on the 8 guard limiters, receiving 70%-80% of the power deposited to the inner wall. In case of shortwave misalignments up to 0.5 mm in the radial direction, calculations show that leading edges are still protected, confirming the robustness of the design.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

10305 - Fluids and plasma physics (including surface physics)

Projekt

<a href="/cs/project/EF16_019%2F0000768" target="_blank" >EF16_019/0000768: COMPASS-U: Tokamak pro špičkový výzkum jaderné fúze</a><br>

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2023

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

194

Číslo periodika v rámci svazku

September

Stát vydavatele periodika

NL - Nizozemsko

Počet stran výsledku

9

Strana od-do

113731

Kód UT WoS článku

000983825900001

EID výsledku v databázi Scopus

2-s2.0-85152238234