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Over the past few years, the preparation of ITER-relevant plasma scenarios has been the main focus of experimental activity on tokamaks. The development of integrated, simultaneous, real-time controls of plasma shape, current, pressure, temperature, radiation, neutron profiles and also impurities, ELMs and MHD are now seen to be essential for further development of quasi-steady state conditions with feedback, or the stabilisation of transient phenomena with event-driven actions. For this thrust, the EFDA JET Real-Time Project has developed a set of real-time plasma measurements, experiment control and communication facilities.
The plasma diagnostics used for real-time experiments are Far Infra Red interferometry, polarimetry, visible, UV and X-ray spectroscopy, LIDAR, bolometry, neutron and magnetics. Further analysis systems produce integrated results, such as temperature profiles on geometry derived from MHD equilibrium solutions.
The actuators include toroidal, poloidal and divertor coils, gas and pellet fuelling, neutral beam injection, radio frequency (ICRH) waves and microwaves (LH). The heating/fuelling operators can either define a power or gas request waveform or select the real-time instantaneous power/gas request from the real-time experiment central control (RTCC) system.
The real-time experiment control system provides both a high-level, control-programming environment and interlocks with the actuators. A MATLAB facility is being developed for the development of more complex controllers.
The plasma measurement, controller and plant control systems communicate in ATM network.
The EFDA Real-Time Project is essential groundwork for future reactors such as ITER. It involves many staff from several institutions. The facility is now frequently used in experiments.
This work has been conducted under the European Fusion Development Agreement and is partly funded by Euratom and the UK Engineering and Physical Sciences Research Council.

Additional information

Authors: FELTON R et al, Euratom/UKAEA Fusion Assoc., Culham Science Centre, Oxon (UK);JOFFRIN E et al, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);ALVES D, Instituto Superor Tecnico, Lisboa (PT);SOUSA J, Instituto Superor Tecnico, Lisboa (PT);MURARI A et al, Consorzio RFX - Associazone EURATOM ENEA sulla Fusione, Padua (IT);ZERBINI M et al, Universite de Nice-Sophia Antipolis, Nice (FR);VITALE E, Associazone EURATOM ENEA sulla Fusione, Frascati (IT);CRISANTI F, Associazone EURATOM ENEA sulla Fusione, Frascati (IT);DE LA LUNA E, Associacion EURATOM CIEMAT para Fusion, Madrid (ES);SANCHEZ J, Associacion EURATOM CIEMAT para Fusion, Madrid (ES)
Bibliographic Reference: An article published in: Fusion Engineering and Design (2005), Volume 74, Issues 1-4, Pages 561-566
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