Influence of hydrogen content in tokamak scrape-off-layer on performance of lithium divertor
Self-replenishing liquid metal coatings are considered as a perspective divertor design able to withstand challenging particle and power loads of a fusion tokamak-reactor. Numerical modeling of the scrape-of-layer (SOL) plasma with advanced 2D codes, such as SOLPS, is necessary for developing of the...
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IOP Publishing
2024-01-01
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| Series: | Nuclear Fusion |
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| Online Access: | https://doi.org/10.1088/1741-4326/ad928a |
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| author | E.D. Marenkov A.A. Pshenov |
| author_facet | E.D. Marenkov A.A. Pshenov |
| author_sort | E.D. Marenkov |
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| description | Self-replenishing liquid metal coatings are considered as a perspective divertor design able to withstand challenging particle and power loads of a fusion tokamak-reactor. Numerical modeling of the scrape-of-layer (SOL) plasma with advanced 2D codes, such as SOLPS, is necessary for developing of the ‘liquid-metal’ divertor. In this work we report on upgraded version of SOLPS 4.3 code liquid metal erosion module implemented earlier in our group and present results of simulations of T-15MD tokamak with Li-covered divertor plates. The erosion model includes all main processes Li erosion, i.e. physical sputtering, thermal sputtering, evaporation, and prompt redeposition. Unlike some other available implementations, Li atoms are considered in kinetic approximation in our version. A detailed analysis of Li erosion and flow in T-15MD configuration for various powers (6–12 MW) and H content in the SOL is presented. It is shown that the most of eroded Li particles are redeposited on the divertor targets, however, in some regimes absolute Li flow from the divertor is still large and might lead to significant main plasma dilution with Li. Vapor shielding effect is pronounced on both divertor targets in the most reasonable regimes providing low peak heat flux values at the target plates, less than 10 MW m ^−2 . The target erosion rate and surface temperatures are within limits of the most target designs. Moreover, in strongly shielded cases the target temperature can be even lower than the Li melting temperature meaning that external heating is required to keep Li flowing. Sensitivity analysis shows that our results are most sensitive to the target heat conduction parameters, i.e. the target thickness, outer surface temperature. It means that controlling the target cooling rate can be a useful tool for controlling the liquid Li divertor regime. Variation of the Li erosion rate parameters has little effect on the divertor performance. |
| format | Article |
| id | doaj-art-e147c0f3bdc34aa4acaca540ec8cef9a |
| institution | OA Journals |
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| language | English |
| publishDate | 2024-01-01 |
| publisher | IOP Publishing |
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| series | Nuclear Fusion |
| spelling | doaj-art-e147c0f3bdc34aa4acaca540ec8cef9a2025-08-20T01:52:49ZengIOP PublishingNuclear Fusion0029-55152024-01-0165101603110.1088/1741-4326/ad928aInfluence of hydrogen content in tokamak scrape-off-layer on performance of lithium divertorE.D. Marenkov0https://orcid.org/0000-0002-8422-8867A.A. Pshenov1https://orcid.org/0000-0001-8527-5940National Nuclear Research University MEPHI , Kashirskoe sh., 31, Moscow, RussiaITER Organization , Route de Vinon-sur-Verdon, CS 90 046, 13067, St. Paul Lez Durance, Cedex, FranceSelf-replenishing liquid metal coatings are considered as a perspective divertor design able to withstand challenging particle and power loads of a fusion tokamak-reactor. Numerical modeling of the scrape-of-layer (SOL) plasma with advanced 2D codes, such as SOLPS, is necessary for developing of the ‘liquid-metal’ divertor. In this work we report on upgraded version of SOLPS 4.3 code liquid metal erosion module implemented earlier in our group and present results of simulations of T-15MD tokamak with Li-covered divertor plates. The erosion model includes all main processes Li erosion, i.e. physical sputtering, thermal sputtering, evaporation, and prompt redeposition. Unlike some other available implementations, Li atoms are considered in kinetic approximation in our version. A detailed analysis of Li erosion and flow in T-15MD configuration for various powers (6–12 MW) and H content in the SOL is presented. It is shown that the most of eroded Li particles are redeposited on the divertor targets, however, in some regimes absolute Li flow from the divertor is still large and might lead to significant main plasma dilution with Li. Vapor shielding effect is pronounced on both divertor targets in the most reasonable regimes providing low peak heat flux values at the target plates, less than 10 MW m ^−2 . The target erosion rate and surface temperatures are within limits of the most target designs. Moreover, in strongly shielded cases the target temperature can be even lower than the Li melting temperature meaning that external heating is required to keep Li flowing. Sensitivity analysis shows that our results are most sensitive to the target heat conduction parameters, i.e. the target thickness, outer surface temperature. It means that controlling the target cooling rate can be a useful tool for controlling the liquid Li divertor regime. Variation of the Li erosion rate parameters has little effect on the divertor performance.https://doi.org/10.1088/1741-4326/ad928adivertorlithiumSOLPSredepositionerosion |
| spellingShingle | E.D. Marenkov A.A. Pshenov Influence of hydrogen content in tokamak scrape-off-layer on performance of lithium divertor Nuclear Fusion divertor lithium SOLPS redeposition erosion |
| title | Influence of hydrogen content in tokamak scrape-off-layer on performance of lithium divertor |
| title_full | Influence of hydrogen content in tokamak scrape-off-layer on performance of lithium divertor |
| title_fullStr | Influence of hydrogen content in tokamak scrape-off-layer on performance of lithium divertor |
| title_full_unstemmed | Influence of hydrogen content in tokamak scrape-off-layer on performance of lithium divertor |
| title_short | Influence of hydrogen content in tokamak scrape-off-layer on performance of lithium divertor |
| title_sort | influence of hydrogen content in tokamak scrape off layer on performance of lithium divertor |
| topic | divertor lithium SOLPS redeposition erosion |
| url | https://doi.org/10.1088/1741-4326/ad928a |
| work_keys_str_mv | AT edmarenkov influenceofhydrogencontentintokamakscrapeofflayeronperformanceoflithiumdivertor AT aapshenov influenceofhydrogencontentintokamakscrapeofflayeronperformanceoflithiumdivertor |