Search Results - "Skinner, C H"
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Recent DIII-D progress toward validating models of tungsten erosion, re-deposition, and migration for application to next-step fusion devices
Published in Materials research express (01-12-2023)“…Abstract Fundamental mechanisms governing the erosion and prompt re-deposition of tungsten impurities in tokamak divertors are identified and analyzed to…”
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2
Transition to ELM-free improved H-mode by lithium deposition on NSTX graphite divertor surfaces
Published in Journal of nuclear materials (15-06-2009)“…Lithium evaporated onto plasma facing components in the NSTX lower divertor has made dramatic improvements in discharge performance. As lithium accumulated,…”
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Journal Article Conference Proceeding -
3
Advances in boronization on NSTX-Upgrade
Published in Nuclear materials and energy (01-08-2017)“…•A new deuterated tri-methyl boron conditioning system was implemented on NSTX-U.•The deposition pattern was characterized vs. experimental conditions.•The…”
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4
Deuterium retention in NSTX with lithium conditioning
Published in Journal of nuclear materials (01-08-2011)“…High (≈90%) deuterium retention was observed in NSTX gas balance measurements both with- and without lithiumization of the carbon plasma-facing components. The…”
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Journal Article Conference Proceeding -
5
Surface chemistry and physics of deuterium retention in lithiated graphite
Published in Journal of nuclear materials (01-08-2011)“…Lithium wall conditioning in TFTR, CDX-U, T-11M, TJ-II and NSTX is found to yield enhanced plasma performance manifest, in part, through improved deuterium…”
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Journal Article Conference Proceeding -
6
NSTX plasma response to lithium coated divertor
Published in Journal of nuclear materials (01-08-2011)“…NSTX experiments have explored lithium evaporated on a graphite divertor and other plasma-facing components in both L- and H- mode confinement regimes heated…”
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Journal Article Conference Proceeding -
7
3D measurements of mobile dust particle trajectories in NSTX
Published in Journal of nuclear materials (15-06-2007)“…The transport of dust particles in plasmas may play a significant role in the performance of next step fusion devices. Highly mobile incandescent dust…”
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Journal Article Conference Proceeding -
8
Effect of lithium PFC coatings on NSTX density control
Published in Journal of nuclear materials (15-06-2007)“…Lithium coatings on the graphite plasma facing components (PFCs) in NSTX are being investigated as a tool for density profile control and reducing the…”
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Journal Article Conference Proceeding -
9
The Materials Analysis Particle Probe (MAPP) Diagnostic System in NSTX
Published in IEEE transactions on plasma science (01-03-2012)“…Lithium conditioning of plasma-facing surfaces has been implemented in National Spherical Torus Experiment (NSTX) leading to improvements in plasma performance…”
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10
3-D reconstruction of pre-characterized lithium and tungsten dust particle trajectories in NSTX
Published in Journal of nuclear materials (01-08-2011)“…Calibrated amounts of 40μm lithium dust and 10μm tungsten powder have been dropped from above into the SOL of the National Spherical Torus Experiment (NSTX) to…”
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Journal Article Conference Proceeding -
11
Raman spectroscopy of carbon dust samples from NSTX
Published in Journal of nuclear materials (30-04-2008)“…The Raman spectrum of dust particles exposed to the NSTX plasma is different from the spectrum of unexposed particles scraped from an unused graphite tile. For…”
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12
Measurements of accumulated metallic impurities during LiTER operation in NSTX
Published in Journal of nuclear materials (15-06-2009)“…Over 100 g of lithium was evaporated onto the NSTX plasma facing components using two stainless steel ovens (LiTER). Plasma emission was recorded using a…”
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Journal Article Conference Proceeding -
13
Large aperture electrostatic dust detector
Published in Journal of nuclear materials (15-05-2008)“…Diagnosis and management of dust inventories generated in next-step magnetic fusion devices is necessary for their safe operation. A novel electrostatic dust…”
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14
Is carbon a realistic choice for ITER's divertor?
Published in Physica scripta (01-05-2006)Get full text
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15
Electrostatic dust detection on remote surfaces
Published in Journal of nuclear materials (15-11-2005)“…The inventory of dust in next-step magnetic fusion devices will be regulated for safety reasons, however diagnostics to measure in-vessel dust are still in…”
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16
Controlling surface dust in a tokamak
Published in Journal of nuclear materials (15-06-2007)“…Methods to measure the inventory of dust particles and to remove dust if it approaches safety limits will be required in next-step tokamaks. A novel…”
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Journal Article Conference Proceeding -
17
Simulations of diffusive lithium evaporation onto the NSTX vessel walls
Published in Journal of nuclear materials (01-08-2011)“…A model for simulating the diffusive evaporation of lithium into a helium filled NSTX vacuum vessel is described and validated against an initial set of…”
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Journal Article Conference Proceeding -
18
Lithium coatings on NSTX plasma facing components and its effects on boundary control, core plasma performance, and operation
Published in Fusion engineering and design (01-11-2010)“…NSTX high power divertor plasma experiments have used in succession lithium pellet injection (LPI), evaporated lithium, and injected lithium powder to apply…”
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Journal Article Conference Proceeding -
19
Pulse-by-pulse measurements of dynamic retention and deposition in NSTX
Published in Journal of nuclear materials (15-06-2007)“…Three quartz crystal microbalances have been deployed in NSTX to measure deposition/erosion in plasma shadowed areas at the upper and lower divertor and…”
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Journal Article Conference Proceeding -
20
Micro-trench measurements of the net deposition of carbon impurity ions in the DIII-D divertor and the resulting suppression of surface erosion
Published in Physica scripta (01-12-2021)“…In this work, we report carbon impurity ion incident angles and deposition rates, along with silicon erosion rates, from measurements of micro-engineered…”
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