The first step of the validation of the recently developed thermal-hydraulic code 4C is presented. We study the transient evolution during a so-called standard 25 kA safety discharge of the International Thermonuclear Experimental Reactor (ITER) Toroidal Field Model Coil (TFMC), tested in 2001–2002 in the TOSKA facility at the Karlsruhe Institute of Technology, Germany. The computed outlet He temperatures from both winding and case cooling channels, as well as the local maximum temperature increase of the structures, are shown to be in good agreement with the measured data
The ITER toroidal field model coil (TFMC) was designed, constructed and tested by the European Home ...
Korea Superconducting Tokamak Advanced Research (KSTAR) began operation in 2008 and is a fully super...
The Divertor Tokamak Test (DTT) facility, a fully superconducting nuclear fusion reactor being built...
The toroidal field model coil (TFMC) was extensively tested in 2001-2002, in the TOSKA facility at t...
Abstract—The first step of the validation of the recently de-veloped thermal-hydraulic code 4C is pr...
The recently developed 4C thermal-hydraulic code, currently under validation, is used to compute the...
We apply the 4C code, recently validated against different types of transients, to the simulation of...
The recently developed and validated 4C code is used to analyse the fast discharge of an ITER TF coi...
The KSTAR tokamak, in operation since 2008 at the National Fusion Research Institute in Korea, is eq...
A new tool – the 4C code – has been developed, which allows the thermal-hydraulic simulation of the ...
The design of a suitable quench protection system is fundamental for the safe operation of supercond...
In the frame of a contract between the ITER (International Thermonuclear Experimental Reactor) Direc...
In the frame of the European DEMO reactor activities, Work Package MAG, superconducting Toroidal Fie...
In the International Thermonuclear Experimental Reactor (ITER), the nuclear radiation escaping from ...
The recently developed 4C thermal-hydraulic code is validated here against experimental data from th...
The ITER toroidal field model coil (TFMC) was designed, constructed and tested by the European Home ...
Korea Superconducting Tokamak Advanced Research (KSTAR) began operation in 2008 and is a fully super...
The Divertor Tokamak Test (DTT) facility, a fully superconducting nuclear fusion reactor being built...
The toroidal field model coil (TFMC) was extensively tested in 2001-2002, in the TOSKA facility at t...
Abstract—The first step of the validation of the recently de-veloped thermal-hydraulic code 4C is pr...
The recently developed 4C thermal-hydraulic code, currently under validation, is used to compute the...
We apply the 4C code, recently validated against different types of transients, to the simulation of...
The recently developed and validated 4C code is used to analyse the fast discharge of an ITER TF coi...
The KSTAR tokamak, in operation since 2008 at the National Fusion Research Institute in Korea, is eq...
A new tool – the 4C code – has been developed, which allows the thermal-hydraulic simulation of the ...
The design of a suitable quench protection system is fundamental for the safe operation of supercond...
In the frame of a contract between the ITER (International Thermonuclear Experimental Reactor) Direc...
In the frame of the European DEMO reactor activities, Work Package MAG, superconducting Toroidal Fie...
In the International Thermonuclear Experimental Reactor (ITER), the nuclear radiation escaping from ...
The recently developed 4C thermal-hydraulic code is validated here against experimental data from th...
The ITER toroidal field model coil (TFMC) was designed, constructed and tested by the European Home ...
Korea Superconducting Tokamak Advanced Research (KSTAR) began operation in 2008 and is a fully super...
The Divertor Tokamak Test (DTT) facility, a fully superconducting nuclear fusion reactor being built...