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Title: Low recycling and high power density handling physics in the Current Drive Experiment-Upgrade with lithium plasma-facing components

Abstract

The Current Drive Experiment-Upgrade [T. Munsat, P. C. Efthimion, B. Jones, R. Kaita, R. Majeski, D. Stutman, and G. Taylor, Phys. Plasmas 9, 480 (2002)] spherical tokamak research program has focused on lithium as a large area plasma-facing component (PFC). The energy confinement times showed a sixfold or more improvement over discharges without lithium PFCs. This was an increase of up to a factor of 3 over ITER98P(y,1) scaling [ITER Physics Basis Editors, Nucl. Fusion 39, 2137 (1999)], and reflects the largest enhancement in confinement ever seen in Ohmic plasmas. Recycling coefficients of 0.3 or below were achieved, and they are the lowest to date in magnetically confined plasmas. The effectiveness of liquid lithium in redistributing heat loads at extremely high power densities was demonstrated with an electron beam, which was used to generate lithium coatings. When directed to a lithium reservoir, evaporation occurred only after the entire volume of lithium was raised to the evaporation temperature. The ability to dissipate a beam power density of about 60 MW/m{sup 2} could have significant consequences for PFCs in burning plasma devices.

Authors:
; ; ; ; ; ; ; ; ; ; ;  [1];  [2];  [2];  [2]
  1. Princeton Plasma Physics Laboratory, Princeton, New Jersey 08543 (United States)
  2. (United States)
Publication Date:
OSTI Identifier:
20975049
Resource Type:
Journal Article
Resource Relation:
Journal Name: Physics of Plasmas; Journal Volume: 14; Journal Issue: 5; Other Information: DOI: 10.1063/1.2718509; (c) 2007 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; BEAM-PLASMA SYSTEMS; COATINGS; CURRENTS; DESIGN; ELECTRON BEAMS; EQUIPMENT; EVAPORATION; FIRST WALL; HEATING LOAD; ITER TOKAMAK; LITHIUM; PLASMA; PLASMA CONFINEMENT; POWER DENSITY; SCALING; SPHERICAL CONFIGURATION; THERMONUCLEAR REACTOR MATERIALS; WALL EFFECTS

Citation Formats

Kaita, R., Majeski, R., Gray, T., Kugel, H., Mansfield, D., Spaleta, J., Timberlake, J., Zakharov, L., Doerner, R., Lynch, T., Maingi, R., Soukhanovskii, V., University of California at San Diego, La Jolla, California 92093, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831, and Lawrence Livermore National Laboratory, Livermore, California 94550. Low recycling and high power density handling physics in the Current Drive Experiment-Upgrade with lithium plasma-facing components. United States: N. p., 2007. Web. doi:10.1063/1.2718509.
Kaita, R., Majeski, R., Gray, T., Kugel, H., Mansfield, D., Spaleta, J., Timberlake, J., Zakharov, L., Doerner, R., Lynch, T., Maingi, R., Soukhanovskii, V., University of California at San Diego, La Jolla, California 92093, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831, & Lawrence Livermore National Laboratory, Livermore, California 94550. Low recycling and high power density handling physics in the Current Drive Experiment-Upgrade with lithium plasma-facing components. United States. doi:10.1063/1.2718509.
Kaita, R., Majeski, R., Gray, T., Kugel, H., Mansfield, D., Spaleta, J., Timberlake, J., Zakharov, L., Doerner, R., Lynch, T., Maingi, R., Soukhanovskii, V., University of California at San Diego, La Jolla, California 92093, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831, and Lawrence Livermore National Laboratory, Livermore, California 94550. Tue . "Low recycling and high power density handling physics in the Current Drive Experiment-Upgrade with lithium plasma-facing components". United States. doi:10.1063/1.2718509.
@article{osti_20975049,
title = {Low recycling and high power density handling physics in the Current Drive Experiment-Upgrade with lithium plasma-facing components},
author = {Kaita, R. and Majeski, R. and Gray, T. and Kugel, H. and Mansfield, D. and Spaleta, J. and Timberlake, J. and Zakharov, L. and Doerner, R. and Lynch, T. and Maingi, R. and Soukhanovskii, V. and University of California at San Diego, La Jolla, California 92093 and Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831 and Lawrence Livermore National Laboratory, Livermore, California 94550},
abstractNote = {The Current Drive Experiment-Upgrade [T. Munsat, P. C. Efthimion, B. Jones, R. Kaita, R. Majeski, D. Stutman, and G. Taylor, Phys. Plasmas 9, 480 (2002)] spherical tokamak research program has focused on lithium as a large area plasma-facing component (PFC). The energy confinement times showed a sixfold or more improvement over discharges without lithium PFCs. This was an increase of up to a factor of 3 over ITER98P(y,1) scaling [ITER Physics Basis Editors, Nucl. Fusion 39, 2137 (1999)], and reflects the largest enhancement in confinement ever seen in Ohmic plasmas. Recycling coefficients of 0.3 or below were achieved, and they are the lowest to date in magnetically confined plasmas. The effectiveness of liquid lithium in redistributing heat loads at extremely high power densities was demonstrated with an electron beam, which was used to generate lithium coatings. When directed to a lithium reservoir, evaporation occurred only after the entire volume of lithium was raised to the evaporation temperature. The ability to dissipate a beam power density of about 60 MW/m{sup 2} could have significant consequences for PFCs in burning plasma devices.},
doi = {10.1063/1.2718509},
journal = {Physics of Plasmas},
number = 5,
volume = 14,
place = {United States},
year = {Tue May 15 00:00:00 EDT 2007},
month = {Tue May 15 00:00:00 EDT 2007}
}