During the integrated commissioning of JT-60SA tokamak, the superconducting magnets have experienced several tests such as current ramps or fast discharges. The time variations of the associated magnetic field have induced AC losses in the winding pack (WP) of the magnets, i.e. hysteresis and coupling losses, and in the casing, i.e. eddy currents losses, of the toroidal field (TF) coils.
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The power exhaust represents a major challenge for the EUropean fusion reactor DEMOnstrator, asking for a new, robust design of the divertor, beyond the solution currently pursued for ITER. For this reason, the construction of a satellite fusion experiment, the Divertor Tokamak Test (DTT) facility, is being pursued in Italy. This compact tokamak, which must be very flexible in terms of plasma...
The “Divertor Tokamak Test” (DTT) is an experimental fusion reactor being built in Frascati (IT) in the framework of the European Fusion Roadmap. The DTT Central Solenoid, used to drive the current in the magnetically coupled plasma, comprises six Nb3Sn layer-wound independently energized modules. Each module is made of three sub-modules: High Field (HF), Medium Field (MF) and Low Field (LF)...
The JT-60 Super Advanced (JT-60SA) magnet system consists of toroidal field (TF) coils, central solenoid (CS), and equilibrium field (EF) coils, and all coils are thermally protected by a thermal shield. The CS consists of four stacked modules with 52 layers, and the conductor is designed with a cable-in-conduit conductor (CICC). The CS is cooled to an operating temperature of 4.5 K by...
The Divertor Tokamak Test (DTT) facility [1], under construction in Frascati, Italy, will rely on a fully-superconductive magnetic system. Thanks to the limited dimension of the machine, three cryo-lines will house all the Feeders for the Central Solenoid (CS), for the Toroidal Field (TF) and for the Poloidal Field (PF) coils, respectively. The in-cryostat route of the different Feeders (two...
The JT-60SA large research tokamak is being constructed by the National Institutes for Quantum and Radiological Science and Technology (QST) in Japan, as a satellite tokamak project designed to complement the International Thermonuclear Experimental Reactor (ITER) and to produce demonstration data for use in the proposed DEMOnstration Power Plants (DEMO). JT-60SA started cool-down phase in...
In the framework of the commissioning of JT-60SA Tokamak (Japan), all the 20 Toroidal Field Coils (TFC) have been tested at Cold Test Facility (CTF, CEA-Saclay) during acceptance quench (with a quench temperature equal to 7.5 K at nominal current). Some complementary tests have been performed (September 2018), on spare coil TFC02 with different quench conditions, especially reduced current (at...
NbTi superconductors with large cross-sectional area of high purity aluminum are used in accelerators, SMES, and fusion devices to improve their stability. The Large Helical Device (LHD) is a Heliotron-type fusion experimental device, which consists of a pair of superconducting helical coils and three pairs of superconducting poloidal coils. The LHD conductor used for the helical coils is a...
Divertor Tokamak Test facility (DTT) is the device devoted to tackle the power exhaust issue in the view of future fusion power plant [1]. The DTT construction is nowadays started in the ENEA site of Frascati, Italy. The DTT superconducting magnet system is comprised of 18 Toroidal Field (TF) coils, able to generate a magnetic field of 6 T at the plasma major radius (i.e., at 2.19 m from the...
JT-60SA is a tokamak magnetic confinement device for plasma experiments. This is one of a joint international research and development projects involving Japan and Europe. JT-60SA adopts superconducting magnets consist of cable-in-conduit conductors. The magnet system consists of 18 Toroidal Field (TF) coils and 4 Central Solenoid (CS) modules, and 6 Equilibrium Field (EF) coils. Poloidal...
Abstract-Experimental Advanced Superconducting Tokamak (EAST) is the first fully superconducting tokamak in the world. The superconducting magnets are made of NbTi Cable-In-Conduit Conductor (CICC). The heat load due to plasma discharge rises the temperature of magnet. If the cooling of magnet is not sufficient and the temperature margin of the superconductive cables is not enough, it maybe...
In the context of tokamak reactors, the Poloidal Field Coils (PFCs) are magnets that surround the Toroidal Field Coil (TFC) assembly and generate a magnetic field which equilibrates the plasma and shapes it into specific forms. To enforce plasma requirements, the six PFCs of the Divertor Tokamak Test (DTT), a facility that will be built at the ENEA research centre in Frascati with the main...
