Dust studies in DIII-D and TEXTOR
Authors:
- D.L. RudakovDRD.L. Rudakov
- A. LitnovskyA. Litnovsky
- W.P. WestWWW.P. West
- J.H. YuJYJ.H. Yu
- J.A. BoedoJBJ.A. Boedo
- B.D. BrayBBB.D. Bray
- S. BrezinsekSBS. Brezinsek
- N.H. BrooksNBN.H. Brooks
- M.E. FenstermacherMFM.E. Fenstermacher
- M. GrothMGM. Groth
- E.M. HollmannEHE.M. Hollmann
- A. HuberAHA. Huber
- 21 July 2009
- journal article
- Published by IOP Publishing in Nuclear Fusion
- Vol. 49 (8)
Abstract
Studies of naturally occurring and artificially introduced carbon dust are conducted in DIII-D and TEXTOR. In DIII-D, dust does not present operational concerns except immediately after entry vents. Submicrometre sized dust is routinely observed using Mie scattering from a Nd : Yag laser. The source is strongly correlated with the presence of type I edge localized modes (ELMs). Larger size (0.005–1 mm diameter) dust is observed by optical imaging, showing elevated dust levels after entry vents. Inverse dependence of the dust velocity on the inferred dust size is found from the imaging data. Heating of the dust particles by the neutral beam injection (NBI) and acceleration of dust particles by the plasma flows are observed. Energetic plasma disruptions produce significant amounts of dust; on the other hand, large flakes or debris falling into the plasma may induce a disruption. Migration of pre-characterized carbon dust is studied in DIII-D and TEXTOR by introducing micrometre-size particles into plasma discharges. In DIII-D, a sample holder filled with 30–40 mg of dust is inserted in the lower divertor and exposed, via sweeping of the strike points, to the diverted plasma flux of high-power ELMing H-mode discharges. After a brief dwell (∼0.1 s) of the outer strike point on the sample holder, part of the dust penetrates into the core plasma, raising the core carbon density by a factor of 2–3 and resulting in a twofold increase in the radiated power. In TEXTOR, instrumented dust holders with 1–45 mg of dust are exposed in the scrape-off-layer 0–2 cm radially outside of the last closed flux surface in discharges heated with 1.4 MW of NBI. Launched in this configuration, the dust perturbed the edge plasma, as evidenced by a moderate increase in the edge carbon content, but did not penetrate into the core plasma.Keywords
This publication has 35 references indexed in Scilit:
- In situ dust detection in fusion devicesPlasma Physics and Controlled Fusion, 2008
- PHYSICS OF DUST IN MAGNETIC FUSION DEVICES2008
- Dust-particle transport in tokamak edge plasmasPhysics of Plasmas, 2005
- Dust in fusion devices—a multi-faceted problem connecting high- and low-temperature plasma physicsPlasma Physics and Controlled Fusion, 2004
- Plasma-material interactions in current tokamaks and their implications for next step fusion reactorsNuclear Fusion, 2001
- Dust particles in controlled fusion devices: morphology, observations in the plasma and influence on the plasma performanceNuclear Fusion, 2001
- Characterization and analysis of dusts produced in three experimental tokamaks: TFTR, DIII-D, and Alcator C-ModFusion Engineering and Design, 2000
- Collection and analysis of particulate from the DIII-D TokamakFusion Engineering and Design, 1998
- High speed cine film studies of plasma behaviour and plasma surface interactions in tokamaksJournal of Nuclear Materials, 1982
- Spatial distribution of limiter material and impurities on the first wall of TFR 400Journal of Nuclear Materials, 1978