Results 1 to 10 of about 304 (249)

Study on divertor detachment and pedestal characteristics in the DIII-D upper closed divertor

open access: yesNuclear Fusion, 2023
Experiments performed in DIII-D demonstrate that higher plasma current and heating power combined with impurity seeding facilitate the achievement of divertor detachment with a higher pedestal pressure and higher plasma performance in H-mode plasmas with
H.Q. Wang   +14 more
exaly   +3 more sources

The effect of impurity seeding into the closed divertor on plasma detachment in the HL-2A tokamak

open access: yesNuclear Fusion, 2023
Recent progress towards an increased understanding of detached divertor physics has been made with the highly closed divertor geometry in HL-2A. Non-intrinsic impurities were injected into the outer divertor chamber, and increased divertor neutral ...
Rui Ke, Na Wu, J M Gao
exaly   +2 more sources

The effect of divertor closure on detachment onset in DIII-D

open access: yesNuclear Materials and Energy, 2019
Experiments at DIII-D use different divertor geometries to measure the effect of divertor closure on detachment onset. We compare matched H-mode discharges in the closed (upper) divertor and the open (lower) divertor and use as a detachment onset metric ...
J G Watkins, A G Mclean, A W Leonard
exaly   +3 more sources

Investigating the role of divertor geometry on density build-up in the island divertor

open access: yesNuclear Materials and Energy
The island divertor has been proposed for power and particle exhaust in stellarators. It is investigated in the Wendelstein 7-X (W7-X) experiment. The divertor capabilities such as particle exhaust or radiative power dissipation scale with the divertor ...
Victoria Winters   +2 more
exaly   +3 more sources

Dependence of particle and power dissipation on divertor geometry and plasma shaping in DIII-D small-angle-slot divertor

open access: yesNuclear Materials and Energy, 2022
Dedicated experiments in DIII-D find that magnetic shaping and divertor target geometry significantly affect the divertor plasma conditions and divertor detachment process in the small-angle-slot (SAS) divertor.
H.Q. Wang   +12 more
doaj   +1 more source

Observation of the Periodical Movement of Ionized Front in a Closed-Divertor Simulator.

open access: yesJournal of Plasma and Fusion Research, 2002
Kazutaka Kawamura   +2 more
exaly   +3 more sources

Measurements of heat flux components due to charged and non-charged particles in DIII-D divertor near and under detachment

open access: yesNuclear Materials and Energy, 2023
Surfacing Eroding Thermocouples (SETC) have been used to provide high spatial and temporal resolution heat flux measurement in DIII-D. SETCs were first tested in the lower divertor of DIII-D using the Divertor Material Evaluation System (DiMES), then an ...
J. Ren   +10 more
doaj   +1 more source

Tungsten erosion and divertor leakage from the DIII-D SAS-VW tungsten-coated divertor in experiments with neon gas seeding

open access: yesNuclear Materials and Energy, 2023
Collector probes have been used to examine tungsten divertor leakage in a variety of scenarios with low-Z impurity seeding during operation with the new tungsten-coated SAS-VW divertor in DIII-D.
Matthew S. Parsons   +15 more
doaj   +1 more source

Modeling the effect of nitrogen recycling on the erosion and leakage of tungsten impurities from the SAS-VW divertor in DIII-D during nitrogen gas injection

open access: yesNuclear Materials and Energy, 2022
The new SAS-VW divertor in DIII-D has tungsten-coated components to enable the study of tungsten erosion and leakage from a closed, slot-like divertor. A proposed method of actively managing the tungsten impurities is to inject low-Z impurities, such as ...
Matthew S. Parsons   +2 more
doaj   +1 more source

Direct measurement of the electron turbulence-broadening edge transport barrier to facilitate core–edge integration in tokamak fusion plasmas

open access: yesNuclear Fusion, 2023
The integration of a high-performance core and a dissipative divertor, or the so-called ‘core–edge integration,’ has been widely identified as a critical gap in the design of future fusion reactors.
H.Q. Wang   +14 more
doaj   +1 more source

Home - About - Disclaimer - Privacy