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Featured researches published by F. Sanchez.


ieee/npss symposium on fusion engineering | 2009

Baseline system design and prototyping for the ITER high-frequency magnetic diagnostics set

D. Testa; R. Chavan; J. Guterl; J.B. Lister; J.-M. Moret; A. Perez; F. Sanchez; B. Schaller; G. Tonetti; M. Toussaint; A. Encheva; G. Vayakis; C. Walker; Y. Fournier; T. Maeder; Hervé Carfantan

This paper reports the mechanical and electrical tests performed for the prototyping of the ITER high-frequency magnetic sensor and the analysis of the measurement performance of this diagnostic. The current design for the sensor is not suitable for manufacturing for ITER due to the high likelihood of breakages of the un-guided tungsten wire during the winding. A number of alternative designs and manufacturing processes have been investigated, with the Low Temperature Co-fired Ceramic technology giving the best results. The measurement performance of the baseline system design for the high-frequency magnetic diagnostic cannot meet the intended ITER requirements due to its intrinsic spatial periodicities.


ieee/npss symposium on fusion engineering | 2009

Progress on the design and manufacturing of the mirrors for the ITER electron cyclotron heating and current drive upper launcher

F. Sanchez; Robert Bertizzolo; R. Chavan; A. Collazos; M. Henderson; Jean-Daniel Landis

Four of the 16 ITER upper port plugs will be devoted to electron cyclotron resonance heating (ECRH) in order to control the magneto-hydrodynamic (MHD) instabilities.


ieee/npss symposium on fusion engineering | 2009

Progress on the ITER electron cyclotron heating and current drive upper launcher steering mirror control system

A. Collazos; Robert Bertizzolo; R. Chavan; F. Dolizy; Faa Federico Felici; T. P. Goodman; Jean-Daniel Landis; F. Sanchez; M. Henderson

The ITER ECRH upper launcher (UL) uses a steering mechanism assembly (SMA) to steer the beams in the appropriate location for controlling magnetohydrodynamic (MHD) activity in the plasma (NTMs and sawtooth oscillations).


ieee npss symposium on fusion engineering | 2005

The Design and Physics Performance of the ITER Upper Port ECH Front Steering Launcher

M. Henderson; R. Chavan; R. Heidinger; G. Ramponi; G. Saibene; F. Sanchez; O. Sauter; H. Shidara; H. Zohm

The purpose of the ITER electron cyclotron resonance heating (ECRH) upper port launcher will be to stabilize the neoclassical tearing mode (NTM) by driving currents (ECCD) locally inside either the q=3/2 or 2 island. In order to deposit current predominately inside the island, a narrow ECCD current deposition profile is required. Also, a wide steering range is desired for application of co-ECCD on the relevant flux surfaces over the wide spectra of possible ITER plasma equilibria. A front steering (FS) launcher has been designed for application on the ITER upper port, offering a wider poloidal steering angle (ges20deg) and a higher ECCD density (factor of 3.0 on average) than the presently planned remote steering (RS) launcher. The launcher is capable of injecting 16 MW per port (eight beams of 2.0 MW) using a two mirror system (1 focusing and 1 steering) for focusing and redirecting the beam towards either the q=3/2 or 2 flux surfaces for all envisioned plasma equilibria. The steering mechanism is bearing-free with flexure pivots, in a compact cartridge capable of plusmn12deg rotation (corresponding to a poloidal steering range of plusmn24deg for the microwave beam). The increased steering range enlarges the range in which the ECCD deposition can be applied, offering the potential to address other physics issues such as sawtooth, FIR or ELM control. The complete design concept and calculated ECCD performance for NTM stabilization will be presented


symposium on fusion technology | 2007

The ECH front steering launcher for the ITER upper port

R. Chavan; M. A. Henderson; Robert Bertizzolo; Jean-Daniel Landis; F. Sanchez; H. Shidara


symposium on fusion technology | 2005

An alternative ECRH front steering launcher for the ITER upper port

R. Chavan; M. A. Henderson; F. Sanchez


symposium on fusion technology | 2009

Design status of the ITER ECRH upper launcher mm-wave system

J-D Landis; R. Chavan; Robert Bertizzolo; A. Collazos; F. Dolizy; Faa Federico Felici; F. Sanchez; M. Henderson


symposium on fusion technology | 2009

Progress on the ITER ECRH upper launcher steering mirror identification and control

A. Collazos; Robert Bertizzolo; R. Chavan; F. Dolizy; Federico Felici; M. Henderson; Jean-Daniel Landis; F. Sanchez


Fusion Engineering and Design | 2011

Assessment of the ITER high-frequency magnetic diagnostic set

D. Testa; Hervé Carfantan; Matthieu Toussaint; R. Chavan; Y. Fournier; J. Guterl; J.B. Lister; Thomas Maeder; J.-M. Moret; A. Perez; F. Sanchez; B. Schaller; C. Slater; M. Stoeck; G. Tonetti


symposium on fusion technology | 2009

Design and manufacturing of the ITER ECRH upper launcher mirrors

F. Sanchez; Robert Bertizzolo; R. Chavan; A. Collazos; M. Henderson; Jean-Daniel Landis

Collaboration


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R. Chavan

École Normale Supérieure

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Robert Bertizzolo

École Polytechnique Fédérale de Lausanne

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A. Collazos

École Polytechnique Fédérale de Lausanne

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Jean-Daniel Landis

École Polytechnique Fédérale de Lausanne

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M. Henderson

École Normale Supérieure

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F. Dolizy

École Polytechnique Fédérale de Lausanne

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J.-M. Moret

École Polytechnique Fédérale de Lausanne

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A. Perez

École Polytechnique Fédérale de Lausanne

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B. Schaller

École Polytechnique Fédérale de Lausanne

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