Conveners
Sat-Mo-Po.03 - Mechanics of Fusion Magnets
- Darren Woulfe (Commonwealth Fusion Systems)
- Trevor Miller (Sumitomo (SHI) Cryogenics Europe Ltd)
The SPARC Central Solenoid Model Coil (CSMC) designed and built by Commonwealth Fusion Systems in collaboration with the Massachusetts Institute of Technology Plasma Science and Fusion Center (MIT PSFC) aims to de-risk design aspects of the SPARC CS. One of the main risks associated with the bucked design of the SPARC tokomak is the large loads from the Toroidal Field magnets on the Central...
IO (ITER Organization) planned cold tests for Toroidal Field (TF) and Poloidal Field (PF1) coils, and a test facility is under development for this specific purpose. The TF coil test campaign foresees a series of tests at half operational current and a final one at full current, 68kA. The latter requires a further development of the facility, due to the severity of the test together with a...
The magnet at the core of the EDIPO2 test facility aims at generating a 15 T background field within a 144×144 mm² aperture and maintaining a field homogeneity length of 900 mm (assuming a 1% drop of the field). Its design features two pairs of flat racetrack coils: one pair (vertical coils) located above and below the aperture, and another pair (side coils) located on its sides. All coils are...
This work investigates the potential advantages of using a High-Temperature Superconducting (HTS) Central Solenoid (CS) in the Divertor Tokamak Test (DTT), an Italian nuclear fusion project based in Frascati, Italy, aiming to complete its engineering design phase by 2025 and construction by 2031. To sustain sufficiently long plasma discharges, the project requires a high-performing CS capable...
The ITER superconducting magnet system comprises 18 Toroidal Field (TF) coils, one Central Solenoid (CS), 6 Poloidal Field (PF) coils, and 18 Correction Coils (CC). These superconducting coils are integrated using robust, flexible structures and over 2,000 high-grade large studs ranging from M56 to M110.
During assembly, these studs are preloaded from hundreds to thousands of kN with...
Fusion magnets for so-called compact high-field machines present a new challenge for designers. Tools for fast assessment of magnet pre-designs are needed, and a new mechanical toolbox called CIRCE has been developed.
New updates to the analysis tool will be presented, including improved winding pack and casing contact, a detailed inner leg interface between adjacent tf coils and...
The design of the DEMO Central Solenoid (CS) poses significant challenges due to the risk of fatigue failure and the stringent design criteria required to mitigate it. These criteria impose constraints on the allowable size of the solenoid, which, in turn, affect the configuration of the toroidal system and influence the overall performance of the fusion reactor. To address these challenges,...
The high field superconducting coils in fusion reactors will require HTS conductor designs that reduce the impact of high screening currents. These screening currents may induce high mechanical stresses, particularly in conductors carrying non-uniform currents under high magnetic fields. This work aims at investigating the current distribution in HTS conductors and mechanical stresses in...
The Levitated Dipole Reactor (LDR) is a promising concept for confining fusion relevant plasmas. In an LDR, a high field dipole magnet (core) is levitated in a large vacuum chamber, mimicking the plasma confinement physics observed in planetary magnetospheres. The performance of an LDR is largely determined by the ability of the core magnet to resist the natural diamagnetic expansion of the...
