Scaling of HeatLMD-simulated impurity outflux from COMPASS-U liquid metal divertor
The result's identifiers
Result code in 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>
Result on the web
<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>
Alternative languages
Result language
angličtina
Original language name
Scaling of HeatLMD-simulated impurity outflux from COMPASS-U liquid metal divertor
Original language description
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.
Czech name
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Czech description
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Classification
Type
J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database
CEP classification
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OECD FORD branch
10305 - Fluids and plasma physics (including surface physics)
Result continuities
Project
<a href="/en/project/GA22-03950S" target="_blank" >GA22-03950S: Plasma interaction with fusion reactor heat shields</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2025
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Nuclear Fusion
ISSN
0029-5515
e-ISSN
1741-4326
Volume of the periodical
65
Issue of the periodical within the volume
1
Country of publishing house
US - UNITED STATES
Number of pages
9
Pages from-to
016014
UT code for WoS article
001356124600001
EID of the result in the Scopus database
2-s2.0-85214912763