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The general control of tokamak plasmas has evolved considerably over the past few years with an increase in the plasma pulse length, an increase in the control of additional heating and fueling, and an increase in the degree to which the shape of the plasma can be varied. The Tokamak Configuration Variable (TCV) is specifically designed to explore the operational benefits of plasma shaping over a wide variety of plasma shapes. Consequently, considerable attention has been given to the control of the poloida

Fully noninductive, steady-state electron cyclotron current drive (ECCD) has been demonstrated for the first time in experiments carried out in the tokamak a configuration variable (TCV) [O. Sauter , Phys. Rev. Lett. 84, 3322 (2000)]. By appropriately distributing six 0.45 MW ECCD sources over the discharge cross section, fully noninductive, stable, and stationary plasmas with I-p up to 210 kA were obtained for the full discharge duration of 1.9 s, corresponding to more than 900 energy confinement times and

A diagnostic neutral beam injector (DNBI) [CRPP report LRP 710/01, CRPP-EPFL, 200 1; EPS Conf. Comr. Fusion Plasma Phys., 25A (2001) 365] has been installed on tokamak A configuration variable (TCV) [Plasma Phys. Control Fusion, 36 (1994) 13277; Plasma Phys. Control Fusion, 43 (200 1) A 16 1; Plasma Phys. Control Fusion, to be published] for the purpose of providing local measurements of plasma ion temperature, velocity and impurity density by Charge exchange recombination spectroscopy (CXRS) [EPS Conf. Con

This paper presents the multiple set of requirements for the ITER magnetic diagnostic systems and the current status of the various R&D activities performed by the EU partners. ...

Albert Perez

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The control of tokamak configuration variable plasmas

Steady-state fully noninductive operation with electron cyclotron current drive and current profile control in the tokamak a configuration variable (TCV)

Upgrade of the diagnostic neutral beam injector for the TCV tokamak

Installation and commissionning of the EU test facility for ITER gyrotron

The Magnetic Diagnostic Set for ITER

The Magnetic Diagnostic Set for ITER

Development of a 2MW, CW coaxial gyrotron at 170GHz and test facility for ITER

The European 2MW, 170GHz Coaxial Cavity Gyrotron for ITER (Invited paper)

Recent results from the EC heated plasmas in the TCV tokamak

Design study of a test stand for ITER gyrotron

Equilibrium and axisymmetric stability of the proposed TCV tokamak

Design and operation of the power installation for the TCV ECRH additional heating

Plasma control experiments on highly shaped TCV tokamak plasmas

Recent results from TCV (Invited Paper)

Creation and control of variably shaped plasmas in TCV

Upgrade of the diagnostic neutral beam injector for the TCV tokamak

19 rectifiers to supply the coils of the TCV tokamak

Control of highly vertically unstable plasmas in TCV with internal coils and fast power supply

A new toroidal plasma experiment for basic collisionless plasma physics

Calculation of induced voltages, currents, and forces due to plasma disruptions in the TCV tokamak, using the TSC code