A review of radiative detachment studies in tokamak advanced magnetic divertor configurations
VA Soukhanovskii - Plasma Physics and Controlled Fusion, 2017 - iopscience.iop.org
The present vision for a plasma–material interface in the tokamak is an axisymmetric
poloidal magnetic X-point divertor. Four tasks are accomplished by the standard poloidal X …
poloidal magnetic X-point divertor. Four tasks are accomplished by the standard poloidal X …
Plasma magnetic control in tokamak devices
G De Tommasi - Journal of Fusion Energy, 2019 - Springer
In tokamak experimental reactors, the magnetic control system is one of the main plasma
control systems that is required, together with the density control, since the very beginning …
control systems that is required, together with the density control, since the very beginning …
ITER-like vertical stabilization system for the EAST Tokamak
A ITER-like vertical stabilization (VS) algorithm has been successfully deployed and
commissioned at EAST. The proposed algorithm decouples the VS from the plasma shape …
commissioned at EAST. The proposed algorithm decouples the VS from the plasma shape …
DTT: a divertor tokamak test facility for the study of the power exhaust issues in view of DEMO
R Albanese, WPDTT2 Team - Nuclear Fusion, 2016 - iopscience.iop.org
In parallel with the programme to optimize the operation with a conventional divertor based
on detached conditions to be tested on the ITER device, a project has been launched to …
on detached conditions to be tested on the ITER device, a project has been launched to …
Design of EAST lower divertor by considering target erosion and tungsten ion transport during the external impurity seeding
To demonstrate the performance of tungsten (W) as the divertor target material and to solve
the power handling problem during high power long-pulse discharge, the upgrade of EAST …
the power handling problem during high power long-pulse discharge, the upgrade of EAST …
Vertical stabilization of tokamak plasmas via extremum seeking
In this paper we propose a vertical stabilization (VS) control system for tokamak plasmas
based on the extremum seeking (ES) algorithm. The gist of the proposed strategy is to inject …
based on the extremum seeking (ES) algorithm. The gist of the proposed strategy is to inject …
A comparative study of the effects of liquid lithium and tin as DEMO divertor targets on the heat loads and SOL properties
The behaviour of the scrape-off plasma of the European tokamak DEMO (DEMOnstration
tokamak of the economical feasibility of the fusion power) is analysed by means of the 2D …
tokamak of the economical feasibility of the fusion power) is analysed by means of the 2D …
The DTT proposal. A tokamak facility to address exhaust challenges for DEMO: Introduction and executive summary
R Albanese, A Pizzuto, WPDTT2 Team - Fusion Engineering and Design, 2017 - Elsevier
As indicated in the European Fusion Roadmap, the main objective of the Divertor Tokamak
Test facility (DTT) is to explore alternative power exhaust solutions for DEMO so as to …
Test facility (DTT) is to explore alternative power exhaust solutions for DEMO so as to …
Progress of divertor heat and particle flux control in EAST for advanced steady-state operation in the last 10 years
L Wang, GS Xu, JS Hu, KD Li, QP Yuan, JB Liu… - Journal of fusion …, 2021 - Springer
Active control of the excessively high heat and particle fluxes on the divertor target plates is
of fundamental importance to the steady state operation of tokamaks, especially for fusion …
of fundamental importance to the steady state operation of tokamaks, especially for fusion …
The first implementation of active detachment feedback control in EAST PCS
QP Yuan, K Wu, L Wang, JC Xu, KD Li, JB Liu… - Fusion Engineering and …, 2020 - Elsevier
Abstract EAST achieved 101.2 seconds H-mode discharge with total power injection up to
3MW in 2017. Consequently to the enhanced auxiliary heating power, the active divertor …
3MW in 2017. Consequently to the enhanced auxiliary heating power, the active divertor …