Divertor impurity seeding with a new feedback control scheme for maintaining good core confinement in grassy-ELM H-mode regime with tungsten monoblock divertor …
Small perturbations and strong impurity exhaust capability associated with the small grassy
ELMs render the grassy-ELM regime a suitable candidate for achieving steady-state H …
ELMs render the grassy-ELM regime a suitable candidate for achieving steady-state H …
Advances in plasma–wall interaction control for H-mode operation over 100 s with ITER-like tungsten divertor on EAST
A total power injection up to 0.3 GJ has been achieved in EAST long pulse H-mode
operation of 101.2 s with an ITER-like water-cooled tungsten (W) mono-block divertor, which …
operation of 101.2 s with an ITER-like water-cooled tungsten (W) mono-block divertor, which …
Advances in the long-pulse steady-state high beta H-mode scenario with active controls of divertor heat and particle fluxes in EAST
BN Wan, XZ Gong, Y Liang, N Xiang, GS Xu… - Nuclear …, 2022 - iopscience.iop.org
Since the last IAEA-Fusion Energy Conference, the Experimental Advanced
Superconducting Tokamak (EAST) research program has been, in support of ITER and …
Superconducting Tokamak (EAST) research program has been, in support of ITER and …
[HTML][HTML] Observation of fully detached divertor integrated with improved core confinement for tokamak fusion plasmas
Integration of divertor detachment with a high-performance (β N∼ 3, β p> 2, H 98∼ 1.5) core
plasma has been demonstrated in DIII-D high-β p (poloidal beta) plasmas associated with a …
plasma has been demonstrated in DIII-D high-β p (poloidal beta) plasmas associated with a …
Compatibility of large ELM control and stable partial detachment with neon/argon seeding in EAST
K Li, X Lin, Z Yang, Q Yang, G Xu, L Meng… - Nuclear …, 2023 - iopscience.iop.org
It is necessary to achieve simultaneous exhaust of excessive transient and steady-state heat
fluxes on the divertor target for the divertor protection in the future fusion reactors. The …
fluxes on the divertor target for the divertor protection in the future fusion reactors. The …
Controlling marginally detached divertor plasmas
A new control system at DIII-D has stabilized the inter-ELM detached divertor plasma state
for H-mode in close proximity to the threshold for reattachment, thus demonstrating the …
for H-mode in close proximity to the threshold for reattachment, thus demonstrating the …
Divertor studies in nitrogen induced completely detached H-modes in full tungsten ASDEX Upgrade
F Reimold, M Wischmeier, M Bernert, S Potzel… - Nuclear …, 2015 - iopscience.iop.org
The first stable completely detached H-mode plasma in the full tungsten ASDEX Upgrade
has been achieved. Complete detachment of both targets is induced by nitrogen seeding …
has been achieved. Complete detachment of both targets is induced by nitrogen seeding …
EAST steady-state long pulse H-mode with core-edge integration for CFETR
XZ Gong, AM Garofalo, J Huang, JP Qian… - Nuclear …, 2022 - iopscience.iop.org
A recent EAST experiment has successfully demonstrated long pulse steady-state high
plasma performance scenario and core-edge integration since the last IAEA in 2018. A …
plasma performance scenario and core-edge integration since the last IAEA in 2018. A …
Integrated exhaust scenarios with actively controlled ELMs
PT Lang, A Kallenbach, J Bucalossi, GD Conway… - Nuclear …, 2005 - iopscience.iop.org
An integrated radiative high performance scenario has been established at ASDEX Upgrade
based on simultaneous feedback control of the average divertor neutral particle and power …
based on simultaneous feedback control of the average divertor neutral particle and power …
Integrated simulations of H-mode operation in ITER including core fuelling, divertor detachment and ELM control
ELM mitigation to avoid melting of the tungsten (W) divertor is one of the main factors
affecting plasma fuelling and detachment control at full current for high Q operation in ITER …
affecting plasma fuelling and detachment control at full current for high Q operation in ITER …