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Integration of full divertor detachment with improved core confinement for tokamak fusion plasmas

Nature communications, 2021-03, Vol.12 (1), p.1365-1365, Article 1365

2021

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Demonstration of Tokamak Discharge Shutdown with Shell Pellet Payload Impurity Dispersal

Physical review letters, 2019-02, Vol.122 (6), p.065001-065001, Article 065001

2019

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Suppression of large edge-localized modes in high-confinement DIII-D plasmas with a stochastic magnetic boundary

Physical review letters, 2004-06, Vol.92 (23), p.235003.1-235003.4, Article 235003

2004

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Resonant Pedestal Pressure Reduction Induced by a Thermal Transport Enhancement due to Stochastic Magnetic Boundary Layers in High Temperature Plasmas

Physical review letters, 2009-10, Vol.103 (16), Article 165005

2009

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Numerical modeling of edge-localized-mode filaments on divertor plates based on thermoelectric currents

Physical review letters, 2010-04, Vol.104 (17), p.175001-175001, Article 175001

2010

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Effect of 3D magnetic perturbations on divertor conditions and detachment in tokamak and stellarator

Plasma physics and controlled fusion, 2017-06, Vol.59 (8), p.84002

2017

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Aspects of three dimensional transport for ELM control experiments in ITER-similar shape plasmas at low collisionality in DIII-D

Plasma physics and controlled fusion, 2008-12, Vol.50 (12), p.124029

2008

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ELM suppression in low edge collisionality H-mode discharges using n = 3 magnetic perturbations

Plasma physics and controlled fusion, 2005-12, Vol.47 (12B), p.B37-B52

2005

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Experimental evidence of enhanced radial transport in small ELM regimes at DIII-D

Physics of plasmas, 2024-02, Vol.31 (2)

2024

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SOL width in limited versus diverted discharges in DIII-D

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S387-S390

2011

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Influence of cross-field drifts and chemical sputtering on simulations of divertor particle and heat loads in ohmic and L-mode plasmas in DIII-D, AUG, and JET using UEDGE

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S530-S534

2011

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ELM-free stationary H-mode plasmas in the ASDEX Upgrade tokamak

Plasma physics and controlled fusion, 2003-08, Vol.45 (8), p.1399-1416

2003

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Particle, heat, and sheath power transmission factor profiles during ELM suppression experiments on DIII-D

Journal of nuclear materials, 2009-06, Vol.390, p.839-842

2009

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Experimental and numerical studies of separatrix splitting and magnetic footprints in DIII-D

Journal of nuclear materials, 2007-06, Vol.363-365, p.570-574

2007

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Reduction of edge-localized mode intensity using high-repetition-rate pellet injection in tokamak H-mode plasmas

Physical review letters, 2013-06, Vol.110 (24), p.245001-245001, Article 245001

2013

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Scaling of divertor heat flux profile widths in DIII-D

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S353-S356

2011

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Compatibility of the radiating divertor with high performance plasmas in DIII-D

Journal of nuclear materials, 2007-06, Vol.363-365, p.416-420

2007

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Modeling of detachment experiments at DIII-D

Journal of nuclear materials, 2015-08, Vol.463, p.569-572

2015

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Micro-trench measurements of the net deposition of carbon impurity ions in the DIII-D divertor and the resulting suppression of surface erosion

Physica scripta, 2021-12, Vol.96 (12), p.124039

2021

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Toroidally resolved structure of divertor heat flux in RMP H-mode discharges on DIII-D

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S901-S905

2011

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First results examining the compatibility of RMP ELM suppression with the radiating divertor in DIII-D

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S906-S909

2011

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Migration of artificially introduced micron-size carbon dust in the DIII-D divertor

Journal of nuclear materials, 2007-06, Vol.363-365, p.227-232

2007

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Quantification of chemical erosion in the DIII-D divertor and implications for ITER

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S141-S144

2011

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Mitigation of tokamak disruptions using high-pressure gas injection

Physical review letters, 2002-07, Vol.89 (5), p.055001-055001, Article 055001

2002

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Tungsten erosion by unipolar arcing in DIII-D

Physica scripta, 2017-12, Vol.T170 (1), p.14034

2017

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Integration of full divertor detachment with improved core confinement for tokamak fusion plasmas

Demonstration of Tokamak Discharge Shutdown with Shell Pellet Payload Impurity Dispersal

Suppression of large edge-localized modes in high-confinement DIII-D plasmas with a stochastic magnetic boundary

Resonant Pedestal Pressure Reduction Induced by a Thermal Transport Enhancement due to Stochastic Magnetic Boundary Layers in High Temperature Plasmas

Numerical modeling of edge-localized-mode filaments on divertor plates based on thermoelectric currents

Effect of 3D magnetic perturbations on divertor conditions and detachment in tokamak and stellarator

Aspects of three dimensional transport for ELM control experiments in ITER-similar shape plasmas at low collisionality in DIII-D

ELM suppression in low edge collisionality H-mode discharges using n = 3 magnetic perturbations

Experimental evidence of enhanced radial transport in small ELM regimes at DIII-D

SOL width in limited versus diverted discharges in DIII-D

Influence of cross-field drifts and chemical sputtering on simulations of divertor particle and heat loads in ohmic and L-mode plasmas in DIII-D, AUG, and JET using UEDGE

ELM-free stationary H-mode plasmas in the ASDEX Upgrade tokamak

Particle, heat, and sheath power transmission factor profiles during ELM suppression experiments on DIII-D

Experimental and numerical studies of separatrix splitting and magnetic footprints in DIII-D

Reduction of edge-localized mode intensity using high-repetition-rate pellet injection in tokamak H-mode plasmas

Scaling of divertor heat flux profile widths in DIII-D

Compatibility of the radiating divertor with high performance plasmas in DIII-D

Modeling of detachment experiments at DIII-D

Micro-trench measurements of the net deposition of carbon impurity ions in the DIII-D divertor and the resulting suppression of surface erosion

Toroidally resolved structure of divertor heat flux in RMP H-mode discharges on DIII-D

First results examining the compatibility of RMP ELM suppression with the radiating divertor in DIII-D

Migration of artificially introduced micron-size carbon dust in the DIII-D divertor

Quantification of chemical erosion in the DIII-D divertor and implications for ITER

Mitigation of tokamak disruptions using high-pressure gas injection

Tungsten erosion by unipolar arcing in DIII-D

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