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Concept
Large Helical Device
Résumé
The Large Helical Device (LHD) is a fusion research device in Toki, Gifu, Japan, belonging to the National Institute for Fusion Science.
It is the second largest superconducting stellarator in the world, after the 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.
Design finalized 1987
Start of construction 1990
Plasma operations from 1998
Neutral beam injection of 3 MW was used in 1999.
In 2005 it maintained a plasma for 3,900 seconds.
In 2006 a new helium cooler was added. Using the new cooler, by 2018 a total of 10 long term operations have been achieved, reaching a maximum power level of 11.833 kA.
To aid public acceptance, an exhaust system was designed to catch and filter the radioactive tritium the fusion process produces.
Source officielle
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