Detachment plasma achieved based on active temperature feedback system in EAST

MW Chen, XZ Gong, KF Gan, L Wang, QP Yuan… - Nuclear …, 2020 - iopscience.iop.org
The infrared (IR) thermography diagnostic has recently been upgraded to achieve real-time
temperature measurement and feedback capability in the experimental advanced …

Approaching detachment in I-mode—response of core confinement and the edge pedestal in the ASDEX Upgrade tokamak

T Happel, ML Reinke, D Silvagni, M Bernert… - Nuclear …, 2021 - iopscience.iop.org
Experiments on nitrogen assisted divertor detachment in the improved energy confinement
mode (I-mode) are reported from the ASDEX Upgrade tokamak. When nitrogen is introduced …

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 …

Active control of divertor asymmetry on EAST by localized D2 and Ar puffing

D Wang, H Guo, H Wang, G Luo, Z Wu, J Wu… - Physics of …, 2011 - pubs.aip.org
, Fusion Eng. Des. 82, 463 (2007)] for both single null (SN) and double null (DN) divertor
configurations. D 2 and Ar puffing at various divertor locations has also been explored as an …

Impacts of recycling impurity on the background ELM behavior during repetitive radiative divertor experiments in EAST

QQ Yang, X Lin, GS Xu, L Zhang, WM Zhang… - Nuclear …, 2023 - iopscience.iop.org
A significant change in the background ELM behavior prior to neon (Ne) seeding has been
observed in a series of repetitive radiative divertor experiments in EAST. With similar …

Compatibility of divertor detachment and ELM suppression in DIII-D high-βp plasmas with ITER-similar shape

D Wu, L Wang, HQ Wang, AM Garofalo, X Gong… - Nuclear …, 2024 - iopscience.iop.org
Integration of transient and steady-state divertor heat fluxes control with a high-performance
core is necessary for future fusion reactors. In recent DIII-D high-βp experiments, divertor …

Modeling of advanced divertor configuration on experimental advanced superconducting tokamak by SOLPS5. 0/B2. 5-Eirene

H Si, HY Guo, GS Xu, BJ Xiao, ZP Luo, Y Guo… - Physics of …, 2016 - pubs.aip.org
Heat exhaust is one of the most challenging issues to be addressed for tokamak magnetic
confinement fusion research. Detailed modeling with SOLPS5. 0/B2. 5-Eirene code package …

Physics design study of the divertor power handling in 8 m class DEMO reactor

K Hoshino, N Asakura, S Tokunaga, Y Homma… - Fusion Engineering and …, 2017 - Elsevier
The divertor plasma performance and the power handling are studied for 8 m class DEMO
reactor with the fusion power of 1.5 GW. Due to the high impurity radiation power (80% of the …

The compatibility of high confinement times and complete divertor detachment in ASDEX-Upgrade

J Neuhauser, M Alexander, G Becker… - Plasma Physics and …, 1995 - iopscience.iop.org
The completely detached high confinement (CDH) regime established recently in high
power ASDEX-Upgrade single null divertor discharges is described. The standard CDH …

Comparison of H-mode plasmas in JET-ILW and JET-C with and without nitrogen seeding

AE Jaervinen, C Giroud, M Groth, P Belo… - Nuclear …, 2016 - iopscience.iop.org
In high confinement mode, highly shaped plasmas with edge localized modes in JET, and
for heating power of 15–17 MW, the edge fluid code EDGE2D-EIRENE predicts transition to …