A new 3D CFD model has been developed and applied to the hydraulic analysis of three different inlet options for the ITER Central Solenoid. From the point of view of flow repartition among the petals, it appears that shorter, more compact options have even a marginal advantage over a long slit inlet; their hydraulic impedance is larger, but always within the allowable. No overheating associated to low n value of the Nb3Sn conductor is predicted for either inlet option
The winding pack of the ITER Toroidal Field (TF) coils is composed of 134 turns of Nb3Sn Cable in Co...
The ITER Central Solenoid (CS) modules are under fabrication by the US ITER organization and its sub...
One of the most challenging components of ITER is the divertor devoted at controlling the characteri...
The final design for the inlets of the supercritical He (SHe) coolant of the toroidal field (TF) sup...
In ITER, the supercritical helium (SHe) coolant enters the superconducting toroidal field (TF) coil...
The combination of the electromagnetic conductor model JackPot ACDC with the thermo-hydraulic model ...
In ITER, so-called “Irregular” Field Joints (IFJs) are foreseen at the interface between irregular s...
The ITER vacuum vessel (VV), located inside the cryostat and housing the in-vessel components, is ma...
The PF-FSJS is a full-size joint sample, based on the NbTi dual-channel cable-in-conduit conductor (...
Abstract: Based on the fabrication methods of forging, drilling and welding, the cooling channels in...
CFD study is done to propose an efficient PCHE (Printed Circuit Heat Exchanger) model; used as a rec...
The current project presents a CFD Benchmark on the Thermal-Hydraulic (TH) performance of ITER’s Vac...
One of the key components regarding heat transfer and tritium inventories in deuterium-tritium nucle...
The thermal hydraulic characteristics of low temperature helium in a Cable-in-Conduit Conductor (CIC...
The ITER Central Solenoid Model Coil (CSMC) is a superconducting magnet, layer-wound two-in-hand usi...
The winding pack of the ITER Toroidal Field (TF) coils is composed of 134 turns of Nb3Sn Cable in Co...
The ITER Central Solenoid (CS) modules are under fabrication by the US ITER organization and its sub...
One of the most challenging components of ITER is the divertor devoted at controlling the characteri...
The final design for the inlets of the supercritical He (SHe) coolant of the toroidal field (TF) sup...
In ITER, the supercritical helium (SHe) coolant enters the superconducting toroidal field (TF) coil...
The combination of the electromagnetic conductor model JackPot ACDC with the thermo-hydraulic model ...
In ITER, so-called “Irregular” Field Joints (IFJs) are foreseen at the interface between irregular s...
The ITER vacuum vessel (VV), located inside the cryostat and housing the in-vessel components, is ma...
The PF-FSJS is a full-size joint sample, based on the NbTi dual-channel cable-in-conduit conductor (...
Abstract: Based on the fabrication methods of forging, drilling and welding, the cooling channels in...
CFD study is done to propose an efficient PCHE (Printed Circuit Heat Exchanger) model; used as a rec...
The current project presents a CFD Benchmark on the Thermal-Hydraulic (TH) performance of ITER’s Vac...
One of the key components regarding heat transfer and tritium inventories in deuterium-tritium nucle...
The thermal hydraulic characteristics of low temperature helium in a Cable-in-Conduit Conductor (CIC...
The ITER Central Solenoid Model Coil (CSMC) is a superconducting magnet, layer-wound two-in-hand usi...
The winding pack of the ITER Toroidal Field (TF) coils is composed of 134 turns of Nb3Sn Cable in Co...
The ITER Central Solenoid (CS) modules are under fabrication by the US ITER organization and its sub...
One of the most challenging components of ITER is the divertor devoted at controlling the characteri...