In the development of the DEMO Physics Basis an important role is played by the prediction of the plasma disruption features and by the evaluation of the electro-magnetic (EM) and thermal loads associated with these events. Indeed, the kind and number of foreseen plasma disruptions drive the development of the DEMO operation scenarios and the design of vessel and in-vessel components. To characterize a plausible macroscopic plasma dynamics during these events, we will carry out an extrapolation from present-day machines of the main parameters characterizing the disruptions: thermal and current quench time, evolution of plasma current, β and li, safety factor limits, halo current fraction and width, radiated heat fraction. In particular, ...
In order to evaluate plasma evolution and in-vessel components strains, a safety code called AINA ha...
A tokamak disruption represents a potential threat to the integrity and availability of fusion react...
In view of the modification to the JET plasma facing components foreseen for the 2004 shutdown, the ...
In the development of the DEMO Physics Basis an important role is played by the prediction of the pl...
Plasma disruptions are one of the major concerns in the design phase of fusion devices. The very hig...
The design study of DEMO is one of the main points of the European Roadmap to Fusion Electricity. Th...
To support the deployment of DEMO wall protection strategy, the development of comprehensive analyse...
A method is developed for the numerical simulation of plasma disruptions in tokamak fusion devices. ...
The protection of the EU-DEMO first wall (FW) during plasma transients represents one of the main ch...
Title: Controlling a burning plasma in the DEMO tokamak away from disruptive eventsF. Janky1, E. Fab...
Accurate modeling of major disruption (MD) and vertical displacement events (VDEs) in ITER is necess...
During plasma disruption events in Tokamaks, a considerable amount of magnetic and thermal energy i...
The analysis of the stresses induced on the vacuum vessel (VV) of a Tokamak and its internal compo...
The currents and forces induced in the tokamak vacuum vessel (wall) during the disruption are calcul...
An essential goal of the EU fusion roadmap is the development of design and technology of a Demonstr...
In order to evaluate plasma evolution and in-vessel components strains, a safety code called AINA ha...
A tokamak disruption represents a potential threat to the integrity and availability of fusion react...
In view of the modification to the JET plasma facing components foreseen for the 2004 shutdown, the ...
In the development of the DEMO Physics Basis an important role is played by the prediction of the pl...
Plasma disruptions are one of the major concerns in the design phase of fusion devices. The very hig...
The design study of DEMO is one of the main points of the European Roadmap to Fusion Electricity. Th...
To support the deployment of DEMO wall protection strategy, the development of comprehensive analyse...
A method is developed for the numerical simulation of plasma disruptions in tokamak fusion devices. ...
The protection of the EU-DEMO first wall (FW) during plasma transients represents one of the main ch...
Title: Controlling a burning plasma in the DEMO tokamak away from disruptive eventsF. Janky1, E. Fab...
Accurate modeling of major disruption (MD) and vertical displacement events (VDEs) in ITER is necess...
During plasma disruption events in Tokamaks, a considerable amount of magnetic and thermal energy i...
The analysis of the stresses induced on the vacuum vessel (VV) of a Tokamak and its internal compo...
The currents and forces induced in the tokamak vacuum vessel (wall) during the disruption are calcul...
An essential goal of the EU fusion roadmap is the development of design and technology of a Demonstr...
In order to evaluate plasma evolution and in-vessel components strains, a safety code called AINA ha...
A tokamak disruption represents a potential threat to the integrity and availability of fusion react...
In view of the modification to the JET plasma facing components foreseen for the 2004 shutdown, the ...