| Large Helical Device | |
|---|---|
 The Large Helical Device in 2014 | |
| Device type | Heliotron |
| Location | Toki, Japan |
| Affiliation | National Institute for Fusion Science |
| Technical specifications | |
| Major radius | 3.9 m (13 ft) |
| Minor radius | 0.6 m (2 ft 0 in) |
| Magnetic field | 3.0 T (30,000 G) |
| History | |
| Year(s) of operation | 1998–present |
The Large Helical Device (大型ヘリカル装置, Ōgata Herikaru Sōchi) (LHD) is a fusion research device located in Toki, Gifu, Japan. It is operated by the National Institute for Fusion Science, and is the world's second-largest superconducting stellarator, after Wendelstein 7-X. The LHD employs a heliotron magnetic field originally developed in Japan.
The objective of the project is to conduct fusion plasma confinement research in a steady state in order to elucidate possible solutions to physics and engineering problems in helical plasma reactors. The LHD uses neutral beam injection, ion cyclotron radio frequency (ICRF), and electron cyclotron resonance heating (ECRH) to heat the plasma, much like conventional tokamaks. The helical divertor heat and particle exhaust system uses the large helical coils to produce a diverting field. This configuration allows for the modification of the stochastic layer size, which is positioned between the confined plasma volume and the field lines that terminate on the divertor plate. Boundary plasma research at LHD focuses on the capability of the helical divertor as an exhaust system for heliotrons and stellarators.[1][2]
- ^ Morisaki, T; et al. (2013). "Initial experiments towards edge plasma control with a closed helical divertor in LHD". Nucl. Fusion. 53 (6): 063014. Bibcode:2013NucFu..53f3014M. doi:10.1088/0029-5515/53/6/063014. S2CID 122537627.
- ^ Bader, Aaron; Effenberg, Florian; Hegna, Chris C. (December 6, 2018). "Progress in Divertor and Edge Transport Research for Stellarator Plasmas" (PDF). Archived from the original (PDF) on 2023-07-26.