Captions in English, showing the participation in JET of the EFDA-JET Associates |
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Austria
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Fast helium-beam plasma spectroscopy: a specific plasma diagnostics to determine
plasma density and temperature profiles, pursued at TU Wien in close cooperation with EFDA-JET
/ Culham. |
In 1997/1998 Böhler Edelstahl AG (Kapfenberg) developed the low-activation
ferritic martensitic steel EUROFER 97, which now serves as one of the European reference structural
materials for fusion. |
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Limiter components for Tore Supra (CEA, France) manufactured by Plansee company
(Reutte, Austria) |
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JET und Österreich |
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Belgium
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Quality of confinement in the Radiative Improved mode. |
RF heating antennae of the TEXTOR tokamak |
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Design of the new ICRH antenna for JET |
Design of the ICRH antenna for ITER |
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JET and Belgium |
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Czech Republic
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Institute of Plasma Physics in Prague |
The small CASTOR tokamak is a very flexible experimental facility |
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Research fission reactor LVR-15 (INR, Rez nr Prague) contributes to selection
of components suitable for the ITER construction |
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JET a Česká republika |
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Denmark
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Computer simulation of fusion plasmas, showing a stable case (left) characterised
by low transport of particles and energy out of the plasma, and a case of turbulence
(right) evolving and causing large transport |
The Risø Collective Thomson Scattering mirror antenna inside TEXTOR
(Germany) |
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JET
og Danmark |
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Finland
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SIMS facility (Secondary Ion Mass Spectrometer) at the VTT Technical Research
Centre of Finland is used to analyse the first wall phenomena in JET such as erosion,
redeposition, hydrogen retention and material transport in the edge region. |
Finnish company Diarc Technology Ltd made tungsten coatings on the JET
divertor tiles. The tiles were removed recently showing that the coating had survived
well over two years of JET operation. |
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JET ja Suomi |
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France
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Tore Supra and its staff (350 people) |
In-vessel view of the Tore Supra with the thermal ring (bottom part)
capable to resist heat flux comparable to the surface of the Sun |
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Superconducting cable for ITER. Association Euratom-CEA has more than 20
years of experience in design, construction and operation of large superconducting magnets. |
Tore Supra in foreground, with impression of ITER at rear of Cadarache
site |
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Le JET et la France |
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Germany
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Plasma vessel of ASDEX Upgrade, Germany’s largest fusion device,
at the Max Planck Institute for Plasma Physics in Garching. Courtesy of IPP Garching |
The TEXTOR tokamak at the Institute for Plasma Physics at Research Centre
Jülich during a construction period for integration of the "Dynamic Ergodic
Divertor" experiment. Courtesy of Research Centre Jülich |
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Electromagnetic coil systems of the "Dynamic Ergodic Divertor" at
TEXTOR before the setting up of protective graphite tiles. The experiment generates perturbing
fields aiming at ergodising the plasma boundary layer. This allows for influencing and
studying the thermal isolation of the fusion plasma and the related energy exhaust as well
as its subsequent deposition onto the surrounding walls. Courtesy of Research Centre Jülich. |
Assembly of the fusion facility Wendelstein 7-X in Greifswald: one of the
50 stellarator coils is being adjusted in one segment of the vacuum vessel. Courtesy of
IPP Greifswald. |
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View to the Tritium Laboratory Karlsruhe (TLK) Courtesy of Research Centre Karlsruhe. |
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JET und Deutschland |
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Greece
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Reciprocating Langmuir probe system designed, constructed and operated by the Plasma Physics
Laboratory at NCSR "Demokritos". The probe is used in conjunction with other
edge-divertor diagnostics to study plasma-surface interactions in tokamaks. |
Langmuir probe head designed for combined electron density, temperature
and flow velocity measurements |
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Port entrance for the probe, permitting access to the divertor of ASDEX
Upgrade tokamak (Germany) |
Reciprocating probe arm in the divertor of ASDEX Upgrade. The arm moves
with a velocity of 3 m/s, sampling the whole divertor region in approximately 280 ms. |
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JET και η Ελλάδα |
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Ireland
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Applied radio-frequency Ion source (ARIS) -
an inductively coupled plasma system with a
cylindrical dielectric tube source and a
diffusion/ion extraction region. |
Capacitive RF ion source (CIRIS) - a cylindrical
plasma system used for investigating the chemical
kinetics of hydrogen plasma |
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JET agus Éire |
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Italy
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Top view of the FTU tokamak in Frascati |
View of the completed reversed-field pinch facility RFX in Padova |
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Vacuum vessel of the RFX facility |
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Il JET et l'Italia |
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Latvia
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Second version of the stand for the liquid metal limiter concept on the
Tokamak ISTTOK – working volume reproduces in scale 1:1 the cross-section of ISTTOK
chamber. |
Liquid metal loop prepared for investigation of corrosion by means of
"washing off" technique |
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JET un Latvija |
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Netherlands
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Plasma modelling code 'Cutie' for the study of turbulence in the fusion
plasma. |
An 'Upper Port Launcher'. This device uses millimeter waves to heat
and control a fusion plasma with high precision. |
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A plasma experiment in the Fusion Road Show |
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| The Pilot experiment for Magnum-PSI, 'Pilot-PSI', a plasma
source which can imitate the conditions in the divertor of ITER. |
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JET en Nederland |
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Poland
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Portable neutron generator for tests of diagnostic systems |
Detectors for registration of high-energy electrons ("runaway
electrons"). The detectors exploit the Cherenkov effect. |
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JET i Polska |
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Portugal
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Tokamak ISTTOK view with its Ion Beam diagnostic on the right. |
General view of the CFN Laboratory with the Tokamak ISTTOK. |
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JET e Portugal |
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Slovenia
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Research Commissioner Potočnik visits Fusion Expo in Slovenia. |
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JET in Slovenija |
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Spain
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View of the Spanish stellarator TJ-II |
Schematic arrangement of the TJ-II coils and plasma (in blue) coiled up around the central
coils. |
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Central coils of the TJ-II stellarator |
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JET y España |
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Sweden
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The reversed-field pinch machine EXTRAP T2R |
The Magnetic Proton Recoil (MPR) neutron spectrometer installed at JET |
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JET och Sverige |
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Switzerland
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The TCV Tokamak, the largest experimental facility at EPFL, can maintain
plasma electric current greater than 1MA for a couple of seconds. Due to its unique
flexibility TCV can produce and control plasmas with very diverse cross-section shapes. |
Heating system of TCV: gyrotrons tuned to 83 GHz (6 sources) and to 118 GHz (3 sources) can deliver in total 4.5 MW of heating power. |
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In SULTAN, CRPP has a world unique facility that allows studies and characterisation
of superconducting cables, of particular relevance for ITER. |
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JET and Switzerland
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United Kingdom
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MAST: The Mega-Amp Spherical Tokamak, operated in UKAEA's Culham Division |
Photograph of a MAST Plasma |
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JET and the UK |
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