Enter your username/e-mail and your new password will be send to you.
|Description||Wendelstein 7-X is a drift-optimized stellarator with a rotational transform close to unity and low magnetic shear suitable for an island divertor. Its core mission is the demonstration of power plant capabilities of optimized stellarators of the modular HELIAS (HELical Advanced Stellarator) concept. It is designed to combine confinement under fusion-relevant conditions, robust equilibrium and stability properties, a feasible exhaust concept, full steady-state technology with superconducting coils, actively cooled in-vessel components, and a continuous wave electron cyclotron resonance heating system. Beyond the validation of stellarator optimization in high-performance discharges, W7-X is to develop integrated steady-state plasma scenarios with high plasma pressure and confinement time, which can be extrapolated to burning fusion plasmas at low collisionality.|
|Status||Operational (2015 - 2015) Being upgraded (2015 - 2016) Under construction (1996 - 2015)|
|Scientific Domains||Physical Sciences and Engineering|
|RI Categorization||Nuclear Research Facilities|
|Location||Wendelsteinstraße 1, Greifswald, 17489, Germany|