A new tool – the 4C code – has been developed, which allows the thermal-hydraulic simulation of the entire superconducting magnet system of the International Thermonuclear Experimental Reactor (ITER), with particular reference to: (1) the winding made of cable-in-conduit conductors (CICC), (2) the structures (the radial plates and the case of the toroidal field – TF – coils, for instance) and (3) the cooling circuits. In this paper the different components of the 4C code (1D 2-channel model of the CICC and of the structure cooling channels, 2D model of selected cross sections of the structures, 0D/1D model of the cryogenic circuit) are described in detail, together with the strategy adopted for the coupling between the different components ...
The recently developed 4C thermal-hydraulic code is validated here against experimental data from th...
Both nuclear fusion and fission devices have to face the issue of the cooling of some critical compo...
Korea Superconducting Tokamak Advanced Research (KSTAR) began operation in 2008 and is a fully super...
A new tool – the 4C code – has been developed, which allows the thermal-hydraulic simulation of the ...
We report on the status of development and first preliminary applications of a new computational too...
In the recent years, the Cryogenic Circuit Conductor and Coil (4C) code has been developed to allow ...
The toroidal field model coil (TFMC) was extensively tested in 2001-2002, in the TOSKA facility at t...
The 4C code was developed to model thermal-hydraulics in superconducting magnet systems and related ...
The cooling of the ITER toroidal field (TF) coils winding pack is guaranteed by the circulation of s...
A new integrated computer code is being developed for the simulations of the overall behavior of the...
The DC performance of the ITER Central Solenoid Insert (CSI) coil, a signle layer solenoid wound usi...
The strands of the Cable-In-Conduit Conductors (CICCs) for the ITER magnet system TF coils are made ...
We apply the 4C code, recently validated against different types of transients, to the simulation of...
In the International Thermonuclear Experimental Reactor (ITER), the nuclear radiation escaping from ...
The ITER superconducting (SC) magnets require the forced flow of supercritical He (SHe) at ~ 4.5 K a...
The recently developed 4C thermal-hydraulic code is validated here against experimental data from th...
Both nuclear fusion and fission devices have to face the issue of the cooling of some critical compo...
Korea Superconducting Tokamak Advanced Research (KSTAR) began operation in 2008 and is a fully super...
A new tool – the 4C code – has been developed, which allows the thermal-hydraulic simulation of the ...
We report on the status of development and first preliminary applications of a new computational too...
In the recent years, the Cryogenic Circuit Conductor and Coil (4C) code has been developed to allow ...
The toroidal field model coil (TFMC) was extensively tested in 2001-2002, in the TOSKA facility at t...
The 4C code was developed to model thermal-hydraulics in superconducting magnet systems and related ...
The cooling of the ITER toroidal field (TF) coils winding pack is guaranteed by the circulation of s...
A new integrated computer code is being developed for the simulations of the overall behavior of the...
The DC performance of the ITER Central Solenoid Insert (CSI) coil, a signle layer solenoid wound usi...
The strands of the Cable-In-Conduit Conductors (CICCs) for the ITER magnet system TF coils are made ...
We apply the 4C code, recently validated against different types of transients, to the simulation of...
In the International Thermonuclear Experimental Reactor (ITER), the nuclear radiation escaping from ...
The ITER superconducting (SC) magnets require the forced flow of supercritical He (SHe) at ~ 4.5 K a...
The recently developed 4C thermal-hydraulic code is validated here against experimental data from th...
Both nuclear fusion and fission devices have to face the issue of the cooling of some critical compo...
Korea Superconducting Tokamak Advanced Research (KSTAR) began operation in 2008 and is a fully super...