Results and future plans of the Lithium Tokamak eXperiment (LTX)
The Lithium Tokamak eXperiment (LTX) is a spherical tokamak with the unique capability of studying the low-recycling regime by coating nearly 90% of the first wall with lithium in either solid or liquid form. Several grams of lithium are evaporated onto the plasma-facing side of the first wall. With...
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Veröffentlicht in: | Journal of nuclear materials 2013-07, Vol.438, p.S1096-S1099 |
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Format: | Artikel |
Sprache: | eng |
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Zusammenfassung: | The Lithium Tokamak eXperiment (LTX) is a spherical tokamak with the unique capability of studying the low-recycling regime by coating nearly 90% of the first wall with lithium in either solid or liquid form. Several grams of lithium are evaporated onto the plasma-facing side of the first wall. Without lithium coatings, the plasma discharge is limited to less than 5ms and only 10kA of plasma current, and the first wall acts as a particle source. With cold lithium coatings, plasma discharges last up to 20ms with plasma currents up to 70kA. The lithium coating provides a low-recycling first wall condition for the plasma and higher fueling rates are required to realize plasma densities similar to that of pre-lithium walls. Traditional puff fueling, supersonic gas injection, and molecular cluster injection (MCI) are used. Liquid lithium experiments will begin in 2012. |
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ISSN: | 0022-3115 1873-4820 |
DOI: | 10.1016/j.jnucmat.2013.01.241 |