In moving towards ITER operation, the detailed analysis of fault conditions for the magnets becomes of increasing importance, to verify that the magnet protection system can safely manage them without any damage to the magnets. A “protected” Loss of Flow Accident in the ITER Toroidal Field (TF) coils, de-tected by the coil flow meters and managed by the Central Inter-lock System, is investigated here using the validated thermal-hydraulic code 4C. We simulate the entire sequence of events that is foreseen to protect the magnet, aiming at verifying the impact on the magnet. The LOFA consequences are investigated in terms of both the temperature margin in the winding pack and of the needed re-cooling time, which will affect the availability of...
In recent years, there has been a growing interest in nuclear fusion as energy source due to its sev...
In the framework of the “roadmap to fusion electricity by 2050”, the design of the European DEMO mac...
The toroidal field model coil (TFMC) was extensively tested in 2001-2002, in the TOSKA facility at t...
In moving towards ITER operation, the detailed analysis of fault conditions for the magnets becomes ...
The ITER tokamak is under construction in France and the EU hopes to produce the first kWh from the ...
The paper analyses the pressurization of the ITER cryostat during an ex-vessel loss of coolant accid...
In nuclear fusion systems, such as ITER, Superconducting Magnets (SMs) will be employed to magnetica...
In the frame of the European DEMO reactor activities, Work Package MAG, superconducting Toroidal Fie...
The superconducting magnet system plays an important role in the framework of the design of the EU D...
The Divertor Tokamak Test (DTT) facility, a fully superconducting nuclear fusion reactor being built...
In the International Thermonuclear Experimental Reactor (ITER), the nuclear radiation escaping from ...
7noThe most promising configuration of a nuclear energy fusion system is the tokamak, the largest of...
The design of a suitable quench protection system is fundamental for the safe operation of supercond...
Superconducting Toroidal Field (TF) coils composed of a winding pack (WP) without radial plates, enc...
ITER (International Thermonuclear Experimental Reactor) is an experimental reactor aimed at demonstr...
In recent years, there has been a growing interest in nuclear fusion as energy source due to its sev...
In the framework of the “roadmap to fusion electricity by 2050”, the design of the European DEMO mac...
The toroidal field model coil (TFMC) was extensively tested in 2001-2002, in the TOSKA facility at t...
In moving towards ITER operation, the detailed analysis of fault conditions for the magnets becomes ...
The ITER tokamak is under construction in France and the EU hopes to produce the first kWh from the ...
The paper analyses the pressurization of the ITER cryostat during an ex-vessel loss of coolant accid...
In nuclear fusion systems, such as ITER, Superconducting Magnets (SMs) will be employed to magnetica...
In the frame of the European DEMO reactor activities, Work Package MAG, superconducting Toroidal Fie...
The superconducting magnet system plays an important role in the framework of the design of the EU D...
The Divertor Tokamak Test (DTT) facility, a fully superconducting nuclear fusion reactor being built...
In the International Thermonuclear Experimental Reactor (ITER), the nuclear radiation escaping from ...
7noThe most promising configuration of a nuclear energy fusion system is the tokamak, the largest of...
The design of a suitable quench protection system is fundamental for the safe operation of supercond...
Superconducting Toroidal Field (TF) coils composed of a winding pack (WP) without radial plates, enc...
ITER (International Thermonuclear Experimental Reactor) is an experimental reactor aimed at demonstr...
In recent years, there has been a growing interest in nuclear fusion as energy source due to its sev...
In the framework of the “roadmap to fusion electricity by 2050”, the design of the European DEMO mac...
The toroidal field model coil (TFMC) was extensively tested in 2001-2002, in the TOSKA facility at t...