A Neutral Beam for the Lithium Tokamak eXperiment Upgrade (LTX-U)
POSTER
Abstract
Neutral beam injection into tokamaks is a proven method of plasma heating and fueling. In LTX, high confinement discharges have been achieved with low-recycling lithium walls. To further improve plasma performance, a neutral beam (NB) will be installed as part of an upgrade to LTX (LTX-U). The NB will provide core plasma fueling with up to 700 kW of injected power. Requirements for accommodating the NB include the addition of injection and beam-dump ports onto the vessel and enhancement of the vacuum vessel pumping capability. Because the NB can also serve as a source of neutrals for charge-exchange recombination spectroscopy, ``active'' spectroscopic diagnostics will also be developed. An overview of these plans and other improvements for upgrading LTX to LTX-U will be presented.
Authors
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Enrique Merino
Princeton Plasma Physics Laboratory (PPPL)
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R. Majeski
Princeton Plasma Physics Laboratory, PPPL, Princeton Plasma Physics Laboratory (PPPL)
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Robert Kaita
Princeton Plasma Physics Laboratory, Princeton Plasma Physics Laboratory (PPPL), PPPL
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Thomas Kozub
Princeton Plasma Physics Laboratory (PPPL)
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D.P. Boyle
Princeton Plasma Physics Laboratory (PPPL), PPPL
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J.C. Schmitt
PPPL, Princeton Plasma Physics Laboratory (PPPL)
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Artem Smirnov
Tri-Alpha Energy, Inc., Tri Alpha Energy, Tri Alpha Energy, Inc.