The Toroidal Field system of the JT-60SA tokamak is composed of 18 NbTi superconducting coils. Half of them are provided by France within the Broader Approach Agreement. These coils are manufactured by General Electric (ex-Alstom) at Belfort, France. Each TF coil is composed of 6 cable-in-conduit conductor lengths, wound in double-pancakes, carrying a nominal current of 25.7 kA. These coils...
Toroidal field (TF) coils are superconductive magnets which create magnetic field to confine plasma in ITER vacuum vessel. In order to confirm TF coil’s functionality, magnetic field created by TF coil need to be evaluated and therefore, accurate measurement of current center line (CCL) is necessary. CCL of TF coil is defined as geometrical barycenter of all the conductors and accurate...
This paper deals with the simulation of the JT-60SA tokamak toroidal field coils test facility in CEA Saclay. To have a better understanding of the thermohydraulic behavior of the coils, a model of the cold test facility cryodistribution coupled to a model of the coils has been developed. Each of the 12 Pancakes is modelled by a 1-D thermohydraulic tube of Simcryogenics code representing the...
The central solenoid (CS) of JT-60SA is composed of the four electrically independent modules, and 6 octa-pancake coils and a quad-pancake coil are assembled vertically in one module. The CS module is supplied with current through the room temperature busbar and current feeder of the superconductor. The withstand voltage for the insulation between the conductors is one of the most important...
The ITER magnet system contains 18 Toroidal Field (TF) coils and each TF winding pack is enclosed in a stainless steel coil case. During plasma operation, the coil case will be subjected to eddy current heating and nuclear heating, in addition to the static heat loads (thermal conduction and radiation). In order to minimize the heat transfer to the superconducting winding pack, the coil case...
In the framework of the EUROfusion DEMO project, studies are conducted in several European institutions for designing the tokamak magnet systems. In order to generate the high magnetic fields required for the plasma confinement and control, the reactor should be equipped with superconducting magnets, the reference design being based on Cable-In-Conduit Conductors (CICC) cooled at cryogenic...
The quench protection system of the non-planar coils of the Wendelstein 7-X stellarator was laid out over fifteen years ago. At that time, the assessment of the hot spot temperature by a basic adiabatic model was done using design values for material and operation parameters. After the operating experience in 2016, the hot spot temperature is re-assessed with the thermal-hydraulic program...
General Atomics (GA) is fabricating the ITER Central Solenoid Modules (CSM). The production contract also includes the design and qualification of tooling necessary for fabrication and full current cold testing. Each of the seven
modules will undergo final testing at GA to verify performance. GA is currently commissioning the Final Test Facility at the CSM Manufacturing site in Poway,...