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
Hauptverfasser: Schmitt, J.C., Abrams, T., Baylor, L.R., Berzak Hopkins, L., Biewer, T., Bohler, D., Boyle, D., Granstedt, E., Gray, T., Hare, J., Jacobson, C.M., Jaworski, M., Kaita, R., Kozub, T., LeBlanc, B., Lundberg, D.P., Lucia, M., Maingi, R., Majeski, R., Merino, E., Ryou, A., Shi, E., Squire, J., Stotler, D., Thomas, C.E., Tritz, K., Zakharov, L.
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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.
ISSN:0022-3115
1873-4820
DOI:10.1016/j.jnucmat.2013.01.241