The discovery of an upward counter flow of helium in the outer annulus of the vertically oriented and top-to-bottom cooled ITER PF-FSJS (Poloidal Field Coil-Full Size Joint Sample) in 2002 led to closer investigations of the effect because it may lead to a reduction of the operational margin of the superconductor used in the ITER environment. Recently, further thermo-hydraulic experiments were carried out on the TFAS2 sample (Toroidal Field Advanced Strand sample 2) with the intent to asses the effect in detail. First investigations confirmed the initial assumption that the origin of the effect lies in the buoyancy of the heated, and thus less dense, helium in the outer annulus of the cable. The helium there is in good contact with the supe...
In an effort to optimise the cryogenics of large superconducting coils for fusion applications (ITER...
The crucial multi-physics problem of how to extrapolate from the performance of an isolated Nb3Sn st...
As a qualification test of ITER-TF coils, each joint sample was tested prior to manufacture of each ...
The discovery of an upward counter flow of helium in the outer annulus of the vertically oriented an...
The PF-FSJS is a full-size joint sample, based on the NbTi dual-channel cable-in-conduit conductor (...
Since year 2009, the joint of the toroidal field (TF) conductor samples tested in the SULTAN facilit...
The final design for the inlets of the supercritical He (SHe) coolant of the toroidal field (TF) sup...
The combination of the electromagnetic conductor model JackPot ACDC with the thermo-hydraulic model ...
The thermal hydraulic characteristics of low temperature helium in a Cable-in-Conduit Conductor (CIC...
The strands of the Cable-In-Conduit Conductors (CICCs) for the ITER magnet system TF coils are made ...
In ITER, the supercritical helium (SHe) coolant enters the superconducting toroidal field (TF) coil...
The Applied Superconductivity Center of the University of Wisconsin-Madison proposes to conduct rese...
In the International Thermonuclear Experimental Reactor (ITER), the nuclear radiation escaping from ...
The cooling of the ITER toroidal field (TF) coils winding pack is guaranteed by the circulation of s...
The Applied Superconductivity Center of the University of Wisconsin-Madison proposes to conduct rese...
In an effort to optimise the cryogenics of large superconducting coils for fusion applications (ITER...
The crucial multi-physics problem of how to extrapolate from the performance of an isolated Nb3Sn st...
As a qualification test of ITER-TF coils, each joint sample was tested prior to manufacture of each ...
The discovery of an upward counter flow of helium in the outer annulus of the vertically oriented an...
The PF-FSJS is a full-size joint sample, based on the NbTi dual-channel cable-in-conduit conductor (...
Since year 2009, the joint of the toroidal field (TF) conductor samples tested in the SULTAN facilit...
The final design for the inlets of the supercritical He (SHe) coolant of the toroidal field (TF) sup...
The combination of the electromagnetic conductor model JackPot ACDC with the thermo-hydraulic model ...
The thermal hydraulic characteristics of low temperature helium in a Cable-in-Conduit Conductor (CIC...
The strands of the Cable-In-Conduit Conductors (CICCs) for the ITER magnet system TF coils are made ...
In ITER, the supercritical helium (SHe) coolant enters the superconducting toroidal field (TF) coil...
The Applied Superconductivity Center of the University of Wisconsin-Madison proposes to conduct rese...
In the International Thermonuclear Experimental Reactor (ITER), the nuclear radiation escaping from ...
The cooling of the ITER toroidal field (TF) coils winding pack is guaranteed by the circulation of s...
The Applied Superconductivity Center of the University of Wisconsin-Madison proposes to conduct rese...
In an effort to optimise the cryogenics of large superconducting coils for fusion applications (ITER...
The crucial multi-physics problem of how to extrapolate from the performance of an isolated Nb3Sn st...
As a qualification test of ITER-TF coils, each joint sample was tested prior to manufacture of each ...