divertor

The plasma facing material in the divertor faces significantly different stresses compared to the majority of the first wall.

In nuclear fusion power research, a divertor is a device that allows online removal of material from the plasma.

The main components are the magnetic coils, cryostat, plasma vessel, divertor and heating systems.

Hydrogen recombination modes are of vital importance in the development of divertor regions for tokamak reactors.

Some critical plasma facing components, such as and in particular the divertor, are typically protected by a different material than that used for the major area of the first wall.

"Large ELMs can damage the plasma facing materials in the divertor, so we must inject pellets at fairly high frequency," says Combs.

Graphite tiles plasma sprayed with tungsten were used for the ASDEX Upgrade divertor.

The advanced, so-called double null divertor plasma configuration has to be maintained through efficient feedback control avoiding plasma disruptions over long discharge durations.

JET was converted to Divertor configuration in 1993 and started operation with ITER-like magnetic configurations in 2006.

ASDEX Upgrade (Axially Symmetric Divertor Experiment)

Many new features like D-T plasma, Test Blanket Module, Biological shielding and an improved divertor will be incorporated in SST-2.

The development of edge-localized modes poses a major challenge in magnetic fusion research with tokamaks, as these instabilities can damage wall components, particularly divertor plates, due to their extremely high energy transfer rate.

A tokamak featuring a divertor is known as a divertor tokamak or divertor configuration tokamak.

Tungsten is used for the divertor in JET, and will be used for the divertor in ITER.

Kay, Michael J. (1998) A Study of Plasma Attenuation and Recombination in the Gas Target Chamber of a Divertor Simulator.

The ULS (UMIST Linear System) is a gas target divertor simulator located on the former UMIST campus of the University of Manchester.

Bolometer for imaging Divertor radiations Almost all of the diagnostic devices installed on SST-1 are indigenous and are designed and developed by Diagnostics Group of Institute for Plasma Research.

ASDEX Upgrade (Axially Symmetric Divertor EXperiment) is a divertor tokamak, that went into operation at the Max-Planck-Institut für Plasmaphysik, Garching in 1991.

The Asdex tokamak at Garching in West Germany has what is known as a 'poloidal divertor' and holds the record for the duration of a plasma in a tokamak - Asdex has sustained its plasma for 10 seconds.

Research on detached plasma and on its recombination modes is of primary importance in order to design an appropriate divertor region in a future nuclear fusion power plant, where huge amounts of energy will be deposited by the fast-moving particles generated in the main reactor.

In 2004 he received the Research Award from the Alexander von Humboldt Foundation for the project "Modelling and Diagnostics of Fusion Edge/divertor plasma" on understanding cold boundary layer plasmas in nuclear fusion reactors performed in collaboration with the Research Centre.

The major goal of the ULS as for many other linear divertor simulators, is to reproduce the same temperature and density conditions of the SOL (Scrape Off Layer) of a tokamak in a linear environment and therefore to make easier the study of its properties.

In the tokamaks ITER and the latest configuration of Joint European Torus, the lowest region of the torus is configured as a divertor, while Alcator C-Mod was built with divertor channels at both top and bottom.

DIII-D has been a major contributor to the world fusion program over the past decade in areas of plasma turbulence, energy and particle transport, electron-cyclotron plasma heating and current drive, plasma stability, and boundary layers physics using a "magnetic divertor" to control the magnetic field configuration at the edge of the plasma.