Liquid metal test divertor in tokamak COMPASS (SPPT 2018, Prague)

Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F18%3A00491927" target="_blank" >RIV/61389021:_____/18:00491927 - isvavai.cz</a>
Result on the web
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DOI - Digital Object Identifier
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Result language
angličtina
Original language name
Liquid metal test divertor in tokamak COMPASS (SPPT 2018, Prague)
Original language description
Předneseno na: SPPT 2018 -Plasma Physics and Technology in Prague ,nSoid metal plasma-facing components in divertors of thermonuclear reactors will marginally survive in ITER, whilst new approaches are required for the more powerful DEMOnstration power plant. We therefore install in tokamak COMPASS divertor a test target based on liquid lithium/tin. We will exposed it to ITER-relevant surface heat flux (20 MW/m2). Based on precisely measured heat fluxes, our simulations predict its easy survival, the surface temperature rises up to 800°C within 120 ms of the standard ELMy H-mode heat flux with ELM filaments reaching hundreds MW/m2. Consequent strong lithium vaporization will be the major operational limit, observed by spectroscopy, fast visible and infrared cameras. The scientific program will focus on operational issues (redeposition of the evaporated metal, ejection of droplets, fast enough liquid refill) as well as on the effect on the plasma physics (improvement of plasma confinement, L-H power thresholdnn
Czech name
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Czech description
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Project
<a href="/en/project/GA16-14228S" target="_blank" >GA16-14228S: Reduction of localised heat loads in divertor of COMPASS tokamak by means of novel active techniques</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Publication year
2018
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

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