L. Cupido A. Cardinali R. Igreja F. Serra M. E. Manso A. Murari JET-EFDA Contributors
The measurement of the fuel mixture remains a very difficult task in thermonuclear plasmas, where the hydrogen isotopes are fully stripped and do not emit line radiation. On the other hand, direct determination of the ion species mix will be essential in the reactor to keep the mixture close to 50/50 and maximize the fusion output. In this paper, t…
PublishedW. Fundamenski
The tokamak plasma boundary, which is typically identified with the area of open field lines known as the scrape-off layer (SOL), determines the degree of plasmawall interaction. SOL physics, much of which is concerned with the exhaust (removal) of particles and energy from the plasma, has been one of the major topics investigated on JET during the…
PublishedR. Nazikian,
Core localized Alfvén eigenmodes in DIII-D [J. L. Luxon, Nucl. Fusion 42 , 614 (2002)] and Joint European Torus JET [P. H. Rebut and B. E. Keen, Fusion Technol. 11 , 13 (1987)] plasmas are driven by deuterium neutral beam ions traveling well below the Alfvén speed. Modes are observed in reverse magnetic shear discharges with deuterium ion velocit…
PublishedL. Meneses L. Cupido A. Sirinelli M. E. Manso JET-EFDA Contributors
We present the main design options and implementation of an X -mode reflectometer developed and successfully installed at JET using an innovative approach. It aims to prove the viability of measuring density profiles with high spatial and temporal resolution using broadband reflectometry operating in long and complex transmission lines. It probes t…
PublishedV. Riccardo
Disruptions lead to the largest operational electromechanical loads on the vessel, its supports, and the in-vessel components. In addition, plasma-facing components can be exposed to very high thermal fluxes during the plasma thermal quench and to high-energy runaway electron beams. Therefore, disruptions represent one of the most demanding design …
PublishedR. J. Buttery R. J. La Haye P. Gohil G. L. Jackson H. Reimerdes E. J. Strait The Diii-D Team
Utilizing a capability to vary neutral beam torque injection in the DIII-D [J. L. Luxon, Nucl. Fusion 42 , 614 (2002)] tokamak, m / n =2/1 neoclassical tearing mode onset thresholds are found to fall by about one unit in βN , from 3 to 2, in ITER-like sawtoothing high-energy confinement modes of plasma operation [R. Aymar, Plasma Phys. Control. Fu…
PublishedH. Tojo A. Ejiri M. P. Gryaznevich Y. Takase Y. Adachi
A method to determine the poloidal mode number m in a spherical tokamak based on magnetic probe data was developed. Perturbed magnetic fields at Mirnov coils are calculated for distributed helical filamentary currents on rational surfaces assuming the maximum current amplitude, m and n toroidal mode number, and the toroidal location of the filament…
Published