Results and future plans of the Lithium Tokamak eXperiment (LTX)

J. C. Schmitt; T. Abrams; L. R. Baylor; L. Berzak Hopkins; T. Biewer; D. Bohler; D. Boyle; E. Granstedt; T. Gray; J. Hare; C. M. Jacobson; M. Jaworski; R. Kaita; T. Kozub; B. LeBlanc; D. P. Lundberg; M. Lucia; R. Maingi; R. Majeski; E. Merino; A. Ryou; E. Shi; J. Squire; D. Stotler; C. E. Thomas; K. Tritz; L. Zakharov

doi:10.1016/j.jnucmat.2013.01.241

Results and future plans of the Lithium Tokamak eXperiment (LTX)

J. C. Schmitt, T. Abrams, L. R. Baylor, L. Berzak Hopkins, T. Biewer, D. Bohler, D. Boyle, E. Granstedt, T. Gray, J. Hare, C. M. Jacobson, M. Jaworski, R. Kaita, T. Kozub, B. LeBlanc, D. P. Lundberg, M. Lucia, R. Maingi, R. Majeski, E. MerinoA. Ryou, E. Shi, J. Squire, D. Stotler, C. E. Thomas, K. Tritz, L. Zakharov

Research output: Contribution to journal › Article › peer-review

19 Scopus citations

Abstract

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 5 ms and only 10 kA of plasma current, and the first wall acts as a particle source. With cold lithium coatings, plasma discharges last up to 20 ms with plasma currents up to 70 kA. 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.

Original language	English
Pages (from-to)	S1096-S1099
Journal	Journal of Nuclear Materials
Volume	438
Issue number	SUPPL
DOIs	https://doi.org/10.1016/j.jnucmat.2013.01.241
State	Published - 2013

Funding

This work supported by USDoE contracts DE-AC02-09CH11466 and DE-AC05-00OR22725.

Funders	Funder number
U.S. Department of Energy	DE-AC05-00OR22725, DE-AC02-09CH11466
U.S. Department of Energy

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

Access to Document

10.1016/j.jnucmat.2013.01.241

Cite this

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., ... Zakharov, L. (2013). Results and future plans of the Lithium Tokamak eXperiment (LTX). Journal of Nuclear Materials, 438(SUPPL), S1096-S1099. https://doi.org/10.1016/j.jnucmat.2013.01.241

@article{3b23132361f94cd1906285825e815515,

title = "Results and future plans of the Lithium Tokamak eXperiment (LTX)",

abstract = "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 5 ms and only 10 kA of plasma current, and the first wall acts as a particle source. With cold lithium coatings, plasma discharges last up to 20 ms with plasma currents up to 70 kA. 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.",

author = "Schmitt, {J. C.} and T. Abrams and Baylor, {L. R.} and {Berzak Hopkins}, L. and T. Biewer and D. Bohler and D. Boyle and E. Granstedt and T. Gray and J. Hare and Jacobson, {C. M.} and M. Jaworski and R. Kaita and T. Kozub and B. LeBlanc and Lundberg, {D. P.} and M. Lucia and R. Maingi and R. Majeski and E. Merino and A. Ryou and E. Shi and J. Squire and D. Stotler and Thomas, {C. E.} and K. Tritz and L. Zakharov",

year = "2013",

doi = "10.1016/j.jnucmat.2013.01.241",

language = "English",

volume = "438",

pages = "S1096--S1099",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier",

number = "SUPPL",

}

Schmitt, JC, Abrams, T, Baylor, LR, Berzak Hopkins, L, Biewer, T, Bohler, D, Boyle, D, Granstedt, E, Gray, T, Hare, J, Jacobson, CM, Jaworski, M, Kaita, R, Kozub, T, LeBlanc, B, Lundberg, DP, Lucia, M, Maingi, R, Majeski, R, Merino, E, Ryou, A, Shi, E, Squire, J, Stotler, D, Thomas, CE, Tritz, K & Zakharov, L 2013, 'Results and future plans of the Lithium Tokamak eXperiment (LTX)', Journal of Nuclear Materials, vol. 438, no. SUPPL, pp. S1096-S1099. https://doi.org/10.1016/j.jnucmat.2013.01.241

TY - JOUR

T1 - Results and future plans of the Lithium Tokamak eXperiment (LTX)

AU - Schmitt, J. C.

AU - Abrams, T.

AU - Baylor, L. R.

AU - Berzak Hopkins, L.

AU - Biewer, T.

AU - Bohler, D.

AU - Boyle, D.

AU - Granstedt, E.

AU - Gray, T.

AU - Hare, J.

AU - Jacobson, C. M.

AU - Jaworski, M.

AU - Kaita, R.

AU - Kozub, T.

AU - LeBlanc, B.

AU - Lundberg, D. P.

AU - Lucia, M.

AU - Maingi, R.

AU - Majeski, R.

AU - Merino, E.

AU - Ryou, A.

AU - Shi, E.

AU - Squire, J.

AU - Stotler, D.

AU - Thomas, C. E.

AU - Tritz, K.

AU - Zakharov, L.

PY - 2013

Y1 - 2013

N2 - 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 5 ms and only 10 kA of plasma current, and the first wall acts as a particle source. With cold lithium coatings, plasma discharges last up to 20 ms with plasma currents up to 70 kA. 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.

AB - 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 5 ms and only 10 kA of plasma current, and the first wall acts as a particle source. With cold lithium coatings, plasma discharges last up to 20 ms with plasma currents up to 70 kA. 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.

UR - http://www.scopus.com/inward/record.url?scp=84885422078&partnerID=8YFLogxK

U2 - 10.1016/j.jnucmat.2013.01.241

DO - 10.1016/j.jnucmat.2013.01.241

M3 - Article

AN - SCOPUS:84885422078

SN - 0022-3115

VL - 438

SP - S1096-S1099

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - SUPPL

ER -

Results and future plans of the Lithium Tokamak eXperiment (LTX)

Abstract

Funding

UN SDGs

Access to Document

Other files and links

Fingerprint

Cite this