0352791 - ÚFP 2011 AT eng C - Conference Paper (international conference)
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OVERVIEW OF PHYSICS RESULTS FROM NSTX.
Contributed Paper 23rd IAEA Fusion Energy Conference. Vienna: International Atomic Energy Agency (IAEA), 2010, OV2-4. IAEA. ISBN N.
[IAEA Fusion Energy Conference /23rd./. Daejon (KR), 11.10.2010-16.10.2010]
R&D Projects: GA ČR GA202/08/0419; GA MŠMT 7G09042
Institutional research plan: CEZ:AV0Z20430508
Keywords : Tokamaks * NSTX * Toroidal confinement * Lithium coatings * Fast Wave heating
Subject RIV: BL - Plasma and Gas Discharge Physics
Result website:
http://www-pub.iaea.org/MTCD/Meetings/PDFplus/2010/cn180/cn180_papers/ov_2-4.pdf

During the last two experimental campaigns, the low aspect-ratio NSTX has explored physics issues critical to both toroidal confinement physics and ITER. Experiments have made extensive use of both lithium coatings for wall conditioning. The resistive wall mode control coils have been used to trigger repetitive ELMs with high reliability. High Harmonic Fast Wave (HHFW) heating produced plasmas with central electron temperatures exceeding 6 keV.
Permanent Link: http://hdl.handle.net/11104/0192216