As a qualification test of ITER-TF coils, each joint sample was tested prior to manufacture of each TF coil. Eleven joint samples were tested by a conductor test facility with a 9 T split coil. The joint sample comprised two short TF conductors that had twin-box joint terminals at both ends. The lower joint is a testing part that is a full-size joint of the TF coil. Hall probes were attached on the lower joint box to measure the field induced by shielding currents. In order to simulate the shielding currents, an equivalent current circuit has been considered. The main loop of the shielding currents is the current flow in two conductors with crossing the jointed plane twice. The other two loops are the current loops inside superconducting ca...
The strands of the Cable-In-Conduit Conductors (CICCs) for the ITER magnet system TF coils are made ...
Abstract: The future magnetic thermonuclear fusion reactors will use superconducting magnets. Th...
The ITER magnet system uses cable-in-conduit conductor (CICC) technology with individual strands twi...
Joint sample tests have been carried out as a qualification test for ITER Toroidal Field (TF) coils....
An ITER Poloidal Field coil winding consists of stacked double pancakes wound with NbTi cable-in-con...
To evaluate the ITER TF joint performance, the joint test sample, which consists of two short TF con...
The European Home Team is responsible for the design, the fabrication and the test of the Toroidal F...
Qualification tests of the ITER toroidal field (TF) conductor joints have been carried out by testin...
One of the critical components of the ITER poloidal field (PF) coils is the electrical joint connect...
Nine toroidal field (TF) coils have been developed in Japan for the international thermonuclear expe...
An improved joint layout layout is proposed for the electrical connections of the large Nb3Sn cable-...
The Poloidal Field (PF) Coil Insert is made from a NbTi cable in conduit conductor and has been subj...
The development of new generation superconducting magnets for fusion research, such as the ITER expe...
We performed simulations with the numerical CUDI-CICC code on a typical short ITER (International Th...
The multistrand NbTi conductors for the Poloidal Field (PF) Coils of the International Thermonuclear...
The strands of the Cable-In-Conduit Conductors (CICCs) for the ITER magnet system TF coils are made ...
Abstract: The future magnetic thermonuclear fusion reactors will use superconducting magnets. Th...
The ITER magnet system uses cable-in-conduit conductor (CICC) technology with individual strands twi...
Joint sample tests have been carried out as a qualification test for ITER Toroidal Field (TF) coils....
An ITER Poloidal Field coil winding consists of stacked double pancakes wound with NbTi cable-in-con...
To evaluate the ITER TF joint performance, the joint test sample, which consists of two short TF con...
The European Home Team is responsible for the design, the fabrication and the test of the Toroidal F...
Qualification tests of the ITER toroidal field (TF) conductor joints have been carried out by testin...
One of the critical components of the ITER poloidal field (PF) coils is the electrical joint connect...
Nine toroidal field (TF) coils have been developed in Japan for the international thermonuclear expe...
An improved joint layout layout is proposed for the electrical connections of the large Nb3Sn cable-...
The Poloidal Field (PF) Coil Insert is made from a NbTi cable in conduit conductor and has been subj...
The development of new generation superconducting magnets for fusion research, such as the ITER expe...
We performed simulations with the numerical CUDI-CICC code on a typical short ITER (International Th...
The multistrand NbTi conductors for the Poloidal Field (PF) Coils of the International Thermonuclear...
The strands of the Cable-In-Conduit Conductors (CICCs) for the ITER magnet system TF coils are made ...
Abstract: The future magnetic thermonuclear fusion reactors will use superconducting magnets. Th...
The ITER magnet system uses cable-in-conduit conductor (CICC) technology with individual strands twi...