Results from recent experiments on the DIII-D tokamak have revealed many important details on transport barriers at the plasma edge and in the plasma core. These experiments include: (a) the formation of the H-mode edge barrier directly by pellet injection; (b) the formation of a quiescent H-mode edge barrier (QH-mode) which is free from edge localized modes (ELMs), but which still exhibits good density and radiative power control; (c) the formation of multiple transport barriers, such as the quiescent double barrier (QDB) which combines a internal transport barrier with the quiescent H-mode edge barrier. Results from the pellet-induced H-mode experiments indicate that: (a) the edge temperature (electron or ion) is not a critical parameter ...
Discharges characteristic of the quiescent double barrier (QDB) regime [1] are attractive for develo...
The effects of changing beam and plasma species on the edge transport barrier are investigated for E...
Abstract. The goals of DIII-D Advanced Tokamak (AT) experiments are to investigate and optimize the ...
High confinement (H-mode) operation is the choice for next-step tokamak devices based either on conv...
Substantial progress has been made towards both understanding and control of internal transport barr...
A key issue for the physics of H-mode plasmas is to determine which plasma quantities are critical f...
Edge conditions in DIII-D are being quantified in order to provide insight into the physics of the H...
Discharges characteristic of the quiescent double barrier (QDB) regime [1] are attractive for develo...
OAK-B135 High confinement mode (H-mode) operation is a leading scenario for burning plasma devices d...
The authors' data indicate that the L-mode to H-mode transition in the DIII-D tokamak is associated ...
The authors report results of experiments to further determine the underlying physics behind the for...
Recent DIII-D experiments have significantly improved the understanding of internal transport barrie...
Recent results from the DIII-D tokamak have provided significant contributions to the understanding ...
Fusion power offers the prospect of abundant, carbon-neutral and sustainable energy. A fusion reacto...
Pellet injection has been employed on DIII-D from different injection locations to optimize the mass...
Discharges characteristic of the quiescent double barrier (QDB) regime [1] are attractive for develo...
The effects of changing beam and plasma species on the edge transport barrier are investigated for E...
Abstract. The goals of DIII-D Advanced Tokamak (AT) experiments are to investigate and optimize the ...
High confinement (H-mode) operation is the choice for next-step tokamak devices based either on conv...
Substantial progress has been made towards both understanding and control of internal transport barr...
A key issue for the physics of H-mode plasmas is to determine which plasma quantities are critical f...
Edge conditions in DIII-D are being quantified in order to provide insight into the physics of the H...
Discharges characteristic of the quiescent double barrier (QDB) regime [1] are attractive for develo...
OAK-B135 High confinement mode (H-mode) operation is a leading scenario for burning plasma devices d...
The authors' data indicate that the L-mode to H-mode transition in the DIII-D tokamak is associated ...
The authors report results of experiments to further determine the underlying physics behind the for...
Recent DIII-D experiments have significantly improved the understanding of internal transport barrie...
Recent results from the DIII-D tokamak have provided significant contributions to the understanding ...
Fusion power offers the prospect of abundant, carbon-neutral and sustainable energy. A fusion reacto...
Pellet injection has been employed on DIII-D from different injection locations to optimize the mass...
Discharges characteristic of the quiescent double barrier (QDB) regime [1] are attractive for develo...
The effects of changing beam and plasma species on the edge transport barrier are investigated for E...
Abstract. The goals of DIII-D Advanced Tokamak (AT) experiments are to investigate and optimize the ...