Scaling of HeatLMD-simulated impurity outflux from COMPASS-U liquid metal divertor

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F25%3A00616629" target="_blank" >RIV/61389021:_____/25:00616629 - isvavai.cz</a>

Výsledek na webu

<a href="https://iopscience.iop.org/article/10.1088/1741-4326/ad8d67" target="_blank" >https://iopscience.iop.org/article/10.1088/1741-4326/ad8d67</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1088/1741-4326/ad8d67" target="_blank" >10.1088/1741-4326/ad8d67</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Scaling of HeatLMD-simulated impurity outflux from COMPASS-U liquid metal divertor

Popis výsledku v původním jazyce

The liquid metal divertor (LMD) concept offers a promising solution to manage extreme heat loads in plasma devices. This study presents predictive simulations using the HeatLMD model for the COMPASS-U tokamak with a full toroidal liquid metal divertor, expected to achieve reactor-relevant divertor heat flux densities. We derive the scaling of the Li|Sn outflux over 7 assumed independent parameters, transferable to other tokamaks. Its transport to LCFS (via ERO2.0) and its radiation (via Aurora and FACIT) predicts acceptably low lithium concentration and negligible plasma cooling. However, for tin, the medium power scenario requires backside cooling beyond the capability of the ITER-like water-cooled divertor, though a temporary heat absorber can approximate this for a 1 s plasma pulse. For incident divertor power exceeding 2 MW and strike point T-e < 10 eV, HeatLMD predicts significant tin plasma radiative disruption.

Název v anglickém jazyce

Scaling of HeatLMD-simulated impurity outflux from COMPASS-U liquid metal divertor

Popis výsledku anglicky

The liquid metal divertor (LMD) concept offers a promising solution to manage extreme heat loads in plasma devices. This study presents predictive simulations using the HeatLMD model for the COMPASS-U tokamak with a full toroidal liquid metal divertor, expected to achieve reactor-relevant divertor heat flux densities. We derive the scaling of the Li|Sn outflux over 7 assumed independent parameters, transferable to other tokamaks. Its transport to LCFS (via ERO2.0) and its radiation (via Aurora and FACIT) predicts acceptably low lithium concentration and negligible plasma cooling. However, for tin, the medium power scenario requires backside cooling beyond the capability of the ITER-like water-cooled divertor, though a temporary heat absorber can approximate this for a 1 s plasma pulse. For incident divertor power exceeding 2 MW and strike point T-e < 10 eV, HeatLMD predicts significant tin plasma radiative disruption.

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/GA22-03950S" target="_blank" >GA22-03950S: Interakce plazmatu s tepelným štítem fúzních reaktorů</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2025

Kód důvěrnosti údajů

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

Název periodika

Nuclear Fusion

ISSN

0029-5515

e-ISSN

1741-4326

Svazek periodika

65

Číslo periodika v rámci svazku

1

Stát vydavatele periodika

US - Spojené státy americké

Počet stran výsledku

9

Strana od-do

016014

Kód UT WoS článku

001356124600001

EID výsledku v databázi Scopus

2-s2.0-85214912763