In the frame of the European DEMO reactor activities, Work Package MAG, superconducting Toroidal Field (TF) coils composed by a graded (Nb3Sn + NbTi) winding pack (WP) without radial plates, encapsulated in a steel casing, are under analysis. The ENEA WP design consists of double-layer wound rectangular cable-in-conduit conductors (CICC), for which operational as well as accidental transients must be carefully investigated. The paper presents the application of the state-of-the-art thermal-hydraulic code 4C to the analysis of the quench propagation inside the WP proposed in 2014 by ENEA. The quench is conservatively initiated at the location of the maximum temperature margin and the voltage, normal zone, hot spot temperature and maximum pre...
The Divertor Tokamak Test (DTT) facility, a fully superconducting nuclear fusion reactor being built...
The recently developed and validated 4C code is used to analyse the fast discharge of an ITER TF coi...
The toroidal field model coil (TFMC) was extensively tested in 2001-2002, in the TOSKA facility at t...
In the frame of the European DEMO reactor activities, Work Package MAG, superconducting Toroidal Fie...
Superconducting Toroidal Field (TF) coils composed of a winding pack (WP) without radial plates, enc...
The design of a suitable quench protection system is fundamental for the safe operation of supercond...
The superconducting magnet system plays an important role in the framework of the design of the EU D...
Three alternative designs of the toroidal field (TF) coil were proposed for the European DEMO being ...
Three design concepts, namely, WP#1, WP#2, and WP#3, for the low-T-c superconductor DEMO toroidal fi...
The European DEMOnstration Fusion Power Plant (EU-DEMO) is being designed as an intermediary stage b...
The European DEMOnstration Fusion Power Plant (EU-DEMO) is planned to be an intermediate step betwee...
The KSTAR tokamak, in operation since 2008 at the National Fusion Research Institute in Korea, is eq...
The recently developed 4C thermal-hydraulic code, currently under validation, is used to compute the...
In the framework of the "roadmap to fusion electricity by 2050", the design of the European DEMO mac...
The first design of the NbTi Poloidal Field (PF) coils for the EU DEMO fusion reactor has been propo...
The Divertor Tokamak Test (DTT) facility, a fully superconducting nuclear fusion reactor being built...
The recently developed and validated 4C code is used to analyse the fast discharge of an ITER TF coi...
The toroidal field model coil (TFMC) was extensively tested in 2001-2002, in the TOSKA facility at t...
In the frame of the European DEMO reactor activities, Work Package MAG, superconducting Toroidal Fie...
Superconducting Toroidal Field (TF) coils composed of a winding pack (WP) without radial plates, enc...
The design of a suitable quench protection system is fundamental for the safe operation of supercond...
The superconducting magnet system plays an important role in the framework of the design of the EU D...
Three alternative designs of the toroidal field (TF) coil were proposed for the European DEMO being ...
Three design concepts, namely, WP#1, WP#2, and WP#3, for the low-T-c superconductor DEMO toroidal fi...
The European DEMOnstration Fusion Power Plant (EU-DEMO) is being designed as an intermediary stage b...
The European DEMOnstration Fusion Power Plant (EU-DEMO) is planned to be an intermediate step betwee...
The KSTAR tokamak, in operation since 2008 at the National Fusion Research Institute in Korea, is eq...
The recently developed 4C thermal-hydraulic code, currently under validation, is used to compute the...
In the framework of the "roadmap to fusion electricity by 2050", the design of the European DEMO mac...
The first design of the NbTi Poloidal Field (PF) coils for the EU DEMO fusion reactor has been propo...
The Divertor Tokamak Test (DTT) facility, a fully superconducting nuclear fusion reactor being built...
The recently developed and validated 4C code is used to analyse the fast discharge of an ITER TF coi...
The toroidal field model coil (TFMC) was extensively tested in 2001-2002, in the TOSKA facility at t...