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Optimization of sensor signals for resistive wall mode control in ITER

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Development of steady-state scenarios compatible with ITER-like wall conditions

Richard Pitts, Gilles Arnoux

A key issue for steady-state tokamak operation is to determine the edge conditions that are compatible both with good core confinement and with the power handling and plasma exhaust capabilities of the plasma facing components (PFCs) and divertor systems. ...

2007

Design status of ITER ECH upper launcher mirrors

René Chavan, Jean-Daniel Landis, Francisco Sanchez, Robert Bertizzolo, Joseph Duron

The ITER ECH upper launcher is devoted to directing up to 8 2NM beams per port plug over half of the plasma cross section. A focusing mirror is used to achieve a very narrow deposition profile to stabilize MHD activity such as the neoclassical tearing mode ...

Ieee Service Center, 445 Hoes Lane, Po Box 1331, Piscataway, Nj 08855-1331 Usa2007

Design status of the ITER ECH upper launcher steering mirror mechanism

René Chavan, Jean-Daniel Landis, Francisco Sanchez, Robert Bertizzolo

The ITER ECRH upper port antenna (or launcher) will be used to drive current locally for stabilising the neoclassical tearing mode (NTM)) by depositing mm-wave power inside of the island which forms on the q=3/2 or 2 rational magnetic flux surfaces and con ...

Ieee Service Center, 445 Hoes Lane, Po Box 1331, Piscataway, Nj 08855-1331 Usa2007

Measurement of edge electrostatic turbulence in the TCV tokamak plasma boundary

Jan Horacek

Almost since the first density profile measurements were made in the scrape-off layer (SOL) of the early tokamaks, it has been recognized that the rate of particle transport perpendicular to magnetic surfaces exceeds that expected on the basis of classical ...

EPFL2006

Stability and toroidal rotation properties of highly shaped plasmas in the TCV tokamak

Andrea Scarabosio

Magnetohydrodynamic (MHD) instabilities and plasma rotation have various impacts on particle and thermal transport in toroidal plasmas. MHD instabilities degrade the confinement, limit the maximum achievable plasma pressure, and can lead to plasma disrupti ...

EPFL2006

Ideal MHD stability of tokamak plasmas with moderate and low aspect ratio

The need of durable and abundant energy sources for future ages stimulates the studies of thermonuclear energy sources, based on hot plasma confinement by magnetic fields. The most developed concept of hot plasma trap is the tokamak, where the plasma confi ...

EPFL2005

Current losses induced by edge localized modes in JET tokamak plasmas

Duccio Testa

We have investigated the effect of edge localized modes (ELMs) on the total plasma current in JET tokamak plasmas using the earth leakage current detection circuit connected to the in-vessel saddle coils. These measurements, and the geometry of the saddle ...

2005

Feedback and rotational stabilization of resistive wall modes in ITER

Jonathan Bryan Lister, Jean-Yves Favez

Different models have been introduced in the stability code MARS-F in order to study the damping effect on resistive wall modes (RWM) in rotating plasmas. Benchmarks of MARS-F calculations with RWM experiments on JET and DIII-D indicate that the semi-kinet ...

2005

Physics of the compact advanced stellarator NCSX

Wilfred Anthony Cooper

Compact optimized stellarators offer novel solutions for confining high-beta plasmas and developing magnetic confinement fusion. The three-dimensional plasma shape can be designed to enhance the magnetohydrodynamic (MHD) stability without feedback or nearb ...

2001

MHD stability limits in the TCV tokamak

Holger Reimerdes

Magnetohydrodynamic (MHD) instabilities can limit the performance and degrade the confinement of tokamak plasmas. The Tokamak à Configuration Variable (TCV), unique for its capability to produce a variety of poloidal plasma shapes, has been used to analyse ...

EPFL2001