Results 1 to 10 of about 299 (260)

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
doaj   +2 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

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 ...
J.M. Gao   +23 more
doaj   +1 more source

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

The ASDEX Upgrade divertor IIb—a closed divertor for strongly shaped plasmas

open access: yesNuclear Fusion, 2003
A new divertor configuration (DIV-IIb) has been implemented in ASDEX Upgrade. In order to accommodate a large variety of plasma shapes with bottom triangularities (δbot) up to 0.48, the outer strikepoint region was modified and the roof baffle was lowered and diminished at its outer part in comparison with the previous divertor (DIV-II). The inner part
Neu, R.   +19 more
openaire   +3 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 ...
A.L. Moser   +4 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

Evaluation of plasma impurity concentration during radiative divertor operation mode on EAST

open access: yesHe jishu, 2022
BackgroundBy injecting gaseous neon (Ne) or argon (Ar) into the divertor region, the radiative divertor operation mode has been successfully realized on experimental advanced superconducting tokamak (EAST).
JI Huajian   +16 more
doaj   +1 more source

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