Concept

Tokamak sphérique

Publications associées (545)

Real Time Hybrid Model Predictive Control for the Current Profile of the Tokamak a Configuration Variable (TCV)

Stefano Coda, Jean-Marc Moret, Hoang Bao Le

Plasma stability is one of the obstacles in the path to the successful operation of fusion devices. Numerical control-oriented codes as it is the case of the widely accepted RZIp may be used within Tokamak simulations. The novelty of this article relies in ...

2016

Saturated ideak kink/peeling formations described as three-dimensional magnetohydrodynamic tokamak equilibrium states

Olivier Sauter, Basil Duval, Jonathan Graves, Wilfred Anthony Cooper, Holger Reimerdes, Laurie Porte, Trach-Minh Tran, David Pfefferlé, Jonathan Marc Philippe Faustin, Hamish William Patten, Daniele Brunetti, Madhusudan Raghunathan, Andreas Kleiner

Free boundary magnetohydrodynamic equilibrium states with spontaneous three dimensional deformations of the plasma-vacuum interface are computed for the first time. The structures obtained have the appearance of saturated ideal external kink/peeling modes. ...

American Institute of Physics2016

Winding Pack Proposal for the TF and CS Coils of European DEMO

Pierluigi Bruzzone, Kamil Sedlák, Rainer Wesche

The design of the European DEMO, i.e., the future fusion tokamak planned after ITER, is being developed under the coordination of the EUROfusion Consortium. This paper reports the design optimization of the toroidal field (TF) winding pack and its correspo ...

2016

Infrared measurements of the heat flux spreading under variable divertor geometries in TCV

Basil Duval, Holger Reimerdes, Benoît Labit, Christian Gabriel Theiler, Umar Sheikh, Federico Nespoli, Roberto Maurizio

The safe and stable operation of a future fusion reactor depends critically on the ability to control the heat loads on the material surfaces facing the plasma. The heat fluxes are particularly high at the strike points in the divertor, where the plasma in ...

2016

High-beta, steady-state hybrid scenario on DIII-D

Holger Reimerdes

The potential of the hybrid scenario (first developed as an advanced inductive scenario for high fluence) as a regime for high-beta, steady-state plasmas is demonstrated on the DIII-D tokamak. These experiments show that the beneficial characteristics of h ...

Iop Publishing Ltd2016

Performance Analysis of Mass-Produced Nb3Sn Conductor for Central Solenoid in ITER

Pierluigi Bruzzone, Kamil Sedlák, Boris Stepanov

The performance of two mass-produced Nb3Sn conductors for the ITER central solenoids was tested for the first timmass-produced Nb3Sn conductorse. One was cut from the forward end of an 80-m-long conductor, and the other was cut from the forward end of a 91 ...

2016

Development and application of Eulerian and Particle-in-Cell gyrokinetic codes for studying the effect of non-adiabatic passing electron dynamics on microturbulence

Julien Stanislas Pierre Dominski

In tokamak fusion plasmas, micro-turbulence transport is known to be the cause of large losses of heat and particles. The present work deals with the study of electrostatic micro-turbulence transport driven by instabilities of essentially two types: the io ...

EPFL2016

Numerical optimization of ramp-down phases for TCV and AUG plasmas

Olivier Sauter, Federico Alberto Alfredo Felici, Antoine Pierre Emmanuel Alexis Merle, Doohyun Kim, Anna Teplukhina

Optimization of the plasma discharge can be defined as determination of an optimal time evolution of the plasma parameters to lead a plasma to a desired state keeping it within the specific limits: physical ones (like the Greenwald density limit, low norma ...

2016

The ITPA disruption database

Jonathan Bryan Lister

A multi-device database of disruption characteristics has been developed under the auspices of the International Tokamak Physics Activity magneto-hydrodynamics topical group. The purpose of this ITPA disruption database (IDDB) is to find the commonalities ...

Iop Publishing Ltd2015

Turbulence simulations of the narrow heat-flux feature in inner-wall limited tokamaks

Federico David Halpern

A recent multi-machine experimental campaign initiated by the ITER Organization concluded that inner-wall limited (IWL) plasmas have a near scrape-off layer (SOL) heat-flux decay length of a few mm's, while the far SOL can have a width of several cm's. The ...

2015

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