Boundary plasma studies for a spherical tokamak with lithium walls
Boundary plasma and plasma-material interactions are investigated for magnetised target fusion (MTF) applications. The General Fusion magnetised target fusion technology uses coaxial helicity injection (CHI) start-up which forms a spherical tokamak in a cavity with liquid lithium walls that will sub...
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Elsevier
2025-03-01
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| Series: | Nuclear Materials and Energy |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S2352179125000250 |
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| author | A. Antony L. Carbajal T.D. Rognlien M.V. Umansky A. Froese S. Howard C. Ribeiro R. Ivanov C. Dunlea C.P. McNally |
| author_facet | A. Antony L. Carbajal T.D. Rognlien M.V. Umansky A. Froese S. Howard C. Ribeiro R. Ivanov C. Dunlea C.P. McNally |
| author_sort | A. Antony |
| collection | DOAJ |
| description | Boundary plasma and plasma-material interactions are investigated for magnetised target fusion (MTF) applications. The General Fusion magnetised target fusion technology uses coaxial helicity injection (CHI) start-up which forms a spherical tokamak in a cavity with liquid lithium walls that will subsequently be compressed to fusion conditions Laberge, J. Fusion Energy (2019) The Plasma Injector 3 (PI3) experiment at General Fusion is a non-compressing experiment with solid lithium walls that studies the formation and quasi-steady state operation of a CHI spherical tokamak Carbajal et al. (2023). An explorative study is carried out for wall-limited versus diverted configurations for PI3 using the fluid edge transport code UEDGE. Experimental edge temperature and density profiles from triple Langmuir probes are used to establish realistic temperature and density profiles in UEDGE Rognlien et al. (1992) by adjusting the transport coefficients. In UEDGE, we model the wall-limited plasma via a thin limiter with various insertion depths. It is found that limiter depth and location are key parameters in determining radial profiles and sputtered lithium behaviour. Furthermore, it is found that the total sputtering of the limiter is significantly lower than the sputtering of the wall in some of the limiter configurations studied. Lithium ions and neutral behaviour are compared between limited and diverted configurations. |
| format | Article |
| id | doaj-art-7daf9705c46a470eaff05b23d08daaf1 |
| institution | Kabale University |
| issn | 2352-1791 |
| language | English |
| publishDate | 2025-03-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Materials and Energy |
| spelling | doaj-art-7daf9705c46a470eaff05b23d08daaf12025-02-04T04:10:27ZengElsevierNuclear Materials and Energy2352-17912025-03-0142101885Boundary plasma studies for a spherical tokamak with lithium wallsA. Antony0L. Carbajal1T.D. Rognlien2M.V. Umansky3A. Froese4S. Howard5C. Ribeiro6R. Ivanov7C. Dunlea8C.P. McNally9General Fusion, 6020 Russ Baker Way, Richmond, V7B 1B4, BC, Canada; Corresponding author.General Fusion, 6020 Russ Baker Way, Richmond, V7B 1B4, BC, CanadaLawrence Livermore National Laboratory, Livermore, 94551, CA, USALawrence Livermore National Laboratory, Livermore, 94551, CA, USAGeneral Fusion, 6020 Russ Baker Way, Richmond, V7B 1B4, BC, CanadaGeneral Fusion, 6020 Russ Baker Way, Richmond, V7B 1B4, BC, CanadaGeneral Fusion, 6020 Russ Baker Way, Richmond, V7B 1B4, BC, CanadaGeneral Fusion, 6020 Russ Baker Way, Richmond, V7B 1B4, BC, CanadaGeneral Fusion, 6020 Russ Baker Way, Richmond, V7B 1B4, BC, CanadaGeneral Fusion, 6020 Russ Baker Way, Richmond, V7B 1B4, BC, CanadaBoundary plasma and plasma-material interactions are investigated for magnetised target fusion (MTF) applications. The General Fusion magnetised target fusion technology uses coaxial helicity injection (CHI) start-up which forms a spherical tokamak in a cavity with liquid lithium walls that will subsequently be compressed to fusion conditions Laberge, J. Fusion Energy (2019) The Plasma Injector 3 (PI3) experiment at General Fusion is a non-compressing experiment with solid lithium walls that studies the formation and quasi-steady state operation of a CHI spherical tokamak Carbajal et al. (2023). An explorative study is carried out for wall-limited versus diverted configurations for PI3 using the fluid edge transport code UEDGE. Experimental edge temperature and density profiles from triple Langmuir probes are used to establish realistic temperature and density profiles in UEDGE Rognlien et al. (1992) by adjusting the transport coefficients. In UEDGE, we model the wall-limited plasma via a thin limiter with various insertion depths. It is found that limiter depth and location are key parameters in determining radial profiles and sputtered lithium behaviour. Furthermore, it is found that the total sputtering of the limiter is significantly lower than the sputtering of the wall in some of the limiter configurations studied. Lithium ions and neutral behaviour are compared between limited and diverted configurations.http://www.sciencedirect.com/science/article/pii/S2352179125000250Plasma-surface interactionDivertorLimiterHeat fluxMagnetised target fusion |
| spellingShingle | A. Antony L. Carbajal T.D. Rognlien M.V. Umansky A. Froese S. Howard C. Ribeiro R. Ivanov C. Dunlea C.P. McNally Boundary plasma studies for a spherical tokamak with lithium walls Nuclear Materials and Energy Plasma-surface interaction Divertor Limiter Heat flux Magnetised target fusion |
| title | Boundary plasma studies for a spherical tokamak with lithium walls |
| title_full | Boundary plasma studies for a spherical tokamak with lithium walls |
| title_fullStr | Boundary plasma studies for a spherical tokamak with lithium walls |
| title_full_unstemmed | Boundary plasma studies for a spherical tokamak with lithium walls |
| title_short | Boundary plasma studies for a spherical tokamak with lithium walls |
| title_sort | boundary plasma studies for a spherical tokamak with lithium walls |
| topic | Plasma-surface interaction Divertor Limiter Heat flux Magnetised target fusion |
| url | http://www.sciencedirect.com/science/article/pii/S2352179125000250 |
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