Spherical torus plasma interactions with large-area liquid lithium surfaces in CDX-U

• Published in: Fusion engineering and design Vol. 61; pp. 217 - 222
• Main Authors: Kaita, R, Majeski, R, Boaz, M, Efthimion, P, Jones, B, Hoffman, D, Kugel, H, Menard, J, Munsat, T, Post-Zwicker, A, Soukhanovskii, V, Spaleta, J, Taylor, G, Timberlake, J, Woolley, R, Zakharov, L, Finkenthal, M, Stutman, D, Antar, G, Doerner, R, Luckhardt, S, Maingi, R, Maiorano, M, Smith, S
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Amsterdam Elsevier B.V 01-11-2002; New York, NY Elsevier Science
• Subjects: Applied sciences; Controled nuclear fusion plants; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Installations for energy generation and conversion: thermal and electrical energy; Lithium limiter; Plasma-surface interactions; Spherical torus; Spherical torus; Lithium limiter; Plasma-surface interactions; Nuclear fusion reactor; Fusion reactor limiters; Lithium; Surface plasma interaction; Nuclear reactor
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/S0920-3796(02)00117-5

The current drive experiment-upgrade (CDX-U) device at the Princeton Plasma Physics Laboratory (PPPL) is a spherical torus (ST) dedicated to the exploration of liquid lithium as a potential solution to reactor first-wall problems such as heat load and erosion, neutron damage and activation, and tritium inventory and breeding. Initial lithium limiter experiments were conducted with a toroidally-local liquid lithium rail limiter (L3) from the University of California at San Diego (UCSD). Spectroscopic measurements showed a clear reduction of impurities in plasmas with the L3, compared to discharges with a boron carbide limiter. The evidence for a reduction in recycling was less apparent, however. This may be attributable to the relatively small area in contact with the plasma, and the presence of high-recycling surfaces elsewhere in the vacuum chamber. This conclusion was tested in subsequent experiments with a fully toroidal lithium limiter that was installed above the floor of the vacuum vessel. The new limiter covered over ten times the area of the L3 facing the plasma. Experiments with the toroidal lithium limiter have recently begun. This paper describes the conditioning required to prepare the lithium surface for plasma operations, and effect of the toroidal liquid lithium limiter on discharge performance.