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A new approach to plasma profile control in ITER

Publications associées (38)

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ADX: a high field, high power density, advanced divertor and RF tokamak

Christian Gabriel Theiler, Francesca Maria Poli, Yu Lin, John Wilson

The MIT Plasma Science and Fusion Center and collaborators are proposing a high-performance Advanced Divertor and RF tokamak eXperiment (ADX)-a tokamak specifically designed to address critical gaps in the world fusion research programme on the pathway to ...

Iop Publishing Ltd2015

R&D around a photoneutralizer-based NBI system (Siphore) in view of a DEMO Tokamak steady state fusion reactor

Ivo Furno, Alan Howling, Philippe Frédérique Bruno Guittienne, Rémy Jacquier

Since the signature of the ITER treaty in 2006, a new research programme targeting the emergence of a new generation of neutral beam (NB) system for the future fusion reactor (DEMO Tokamak) has been underway between several laboratories in Europe. The spec ...

Iop Publishing Ltd2015

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The 24 MW ITER Electron Cyclotron (EC) Heating and Current Drive (H&CD) system, operating at 170 GHz, consists of one Equatorial (EL) and four Upper Launchers (UL). The main task of the UL will be the control of Magneto-Hydrodynamic (MHD) activity such as ...

E D P Sciences2015

Real-time sawtooth control and NTM preemption in ITER

Olivier Sauter, Timothy Goodman, Doohyun Kim, Donghyun Kim

Real-time control of multiple plasma actuators is a requirement in advanced tokamaks; for example, for burn control, plasma current profile control and MHD stabilizationelectron cyclotron (EC) wave absorption is ideally suited especially for the latter. O ...

Amer Inst Physics2014

An active plasma profile control approach for ITER, which is potentially robust by being tolerant to changing and uncertain physics, has been explored in this work, using a technique based on real-time estimation of linearized profile response models. The ...

2012

The ITER Plasma Control System (PCS) requires an extensive set of about 50 diagnostic systems to measure the plasma response and about 20 actuators to act on the plasma to carry out its control functions. The specifications and real limitations of the actu ...

Elsevier Science Sa2012

High Density Plasma Heating in the Tokamak à Configuration Variable

Loïc Curchod

The Tokamak à Configuration Variable (TCV) is a medium size magnetic confinement thermonuclear fusion experiment designed for the study of the plasma performances as a function of its shape. It is equipped with a high power and highly flexible electron cyc ...

EPFL2011

Balancing current drive and heating in DIII-D high noninductive current fraction discharges through choice of the toroidal field

Holger Reimerdes

In order to maintain stationary values of the stored energy and the plasma current in a tokamak discharge with all of the current driven noninductively, the sum of the α-heating power and the power required to provide externally driven current must be equa ...

2011

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The Electron Cyclotron (EC) system for the ITER tokamak is designed to inject >= 20 MW RF power into the plasma for Heating and Current Drive (H&CD) applications. The EC system consists of up to 26 gyrotrons (between 1 and 2 MW each), the associated power ...

Elsevier2011

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In the standard scenario of tokamak plasma operation, sawtooth crashes are the main perturbations that can trigger performance-degrading, and potentially disruption-generating, neoclassical tearing modes. This Letter demonstrates sawtooth pacing by real-ti ...

American Physical Society2011