Results 21 to 30 of about 744 (275)

Challenges and approaches to interpretive modeling of boundary plasma and neutral transport in a closed, pumped divertor

open access: yesNuclear Fusion
An experimental discharge from the DIII-D tokamak is modeled using the SOLPS-ITER code suite and compared against measurements in the pumped and relatively closed upper divertor.
R.S. Wilcox   +8 more
doaj   +2 more sources

Effect of divertor legs on neutral particle and impurity retention for a closed helical divertor configuration in the Large Helical Device

open access: yesEffect of divertor legs on neutral particle and impurity retention for a closed helical divertor configuration in the Large Helical Device
A closed helical divertor (CHD) has been designed for efficient particle control in the plasma periphery and for retaining neutral particles and impurity ions in the divertor region.
LHD, Experiment Group   +5 more
core   +1 more source

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

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

Initial TCV operation with a baffled divertor

open access: yes, 2021
The Tokamak à Configuration Variable (TCV) tokamak is in the midst of an upgrade to further its capability to investigate conventional and alternative divertor configurations. To that end, modular and removable gas baffles have been installed to decrease
Bagnato, F.   +59 more
core   +5 more sources

Investigation of the Helical Divertor Function and the Future Plan of a Closed Divertor for Efficient Particle Control in the LHD Plasma Periphery

open access: yesInvestigation of the Helical Divertor Function and the Future Plan of a Closed Divertor for Efficient Particle Control in the LHD Plasma Periphery
The function of the divertor plasmas on the particle control in the plasma periphery is investigated from viewpoints of magnetic field line structures and neutral particle transport in the Large Helical Device (LHD).
SAKAUE, A   +9 more
core   +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

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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