Results 1 to 10 of about 812,697 (276)

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

Nuclear 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, D.M. Thomas, A.W. Leonard, X.X. Ma, H.Y. Guo, A.L. Moser, J.G. Watkins, F. Scotti, C. Lasnier, M.E. Fenstermacher, A.G. McLean, M.W. Shafer, B. Grierson, J. Ren, T.H. Osborne   +14 more
exaly   +4 more sources

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

Nuclear 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   +3 more sources

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

Nuclear 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, Valeria Perseo, Yuhe Feng   +2 more
exaly   +4 more sources

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

Nuclear 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, A G McLean, H Q Wang
exaly   +3 more sources

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

Nuclear 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, X. Ma, R. Maurizio, H.Y. Guo, D.M. Thomas, J.G. Watkins, M.W. Shafer, A.W. Hyatt, A.L. Moser, J. Ren, A. McLean, F. Scotti, P. Stangeby   +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

Nuclear 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, D.C. Donovan, J.G. Watkins, H.Q. Wang, X.X. Ma, R. Maurizio, M.W. Shafer, D. Rudakov, P.C. Stangeby, D. Thomas, S. Hong   +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

Nuclear 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, Jeremy D. Mateja, Seth H. Messer, Tyler Abrams, Jean Paul Allain, Alessandro Bortolon, Patrick Byrne, David C. Donovan, Florian Effenberg, Jeffrey L. Herfindal, Florian Laggner, Tomas Odstrcil, Jun Ren, Dmitry L. Rudakov, Gregory Sinclair, Robert S. Wilcox   +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

Nuclear 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, Gregory Sinclair, Tyler Abrams   +2 more
doaj   +1 more source

Boron transport simulation using the ERO2.0 code for real-time wall conditioning in the large helical device

Nuclear Materials and Energy, 2020
The three-dimensional Monte-Carlo impurity transport and plasma surface interaction code ERO2.0 is applied to a full-torus model for the Large Helical Device (LHD).
M. Shoji, G. Kawamura, J. Romazanov, A. Kirschner, A. Eksaeva, D. Borodin, S. Masuzaki, S. Brezinsek   +7 more
doaj   +1 more source

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

Nuclear 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, R. Hong, X. Jian, T.L. Rhodes, H.Y. Guo, A.W. Leonard, X. Ma, J.G. Watkins, J. Ren, B.A. Grierson, M.W Shafer, F. Scotti, T.H. Osborne, D.M. Thomas, Z. Yan   +14 more
doaj   +1 more source