Zobrazeno 1 - 10
of 109
pro vyhledávání: '"Ph. Moreau"'
Autor:
G. Bodner, A. Gallo, A. Diallo, R. Lunsford, Ph. Moreau, A. Nagy, F.-P. Pellissier, C. Guillemaut, J.P. Gunn, C. Bourdelle, C. Desgranges, P. Manas, A. Bortolon, C.C. Klepper, E. Tsitrone, E.A. Unterberg, L. Vermare, null the WEST Team
Publikováno v:
Nuclear Fusion
Nuclear Fusion, 2022, 62, pp.086020. ⟨10.1088/1741-4326/ac70ea⟩
Nuclear Fusion, 2022, 62, pp.086020. ⟨10.1088/1741-4326/ac70ea⟩
Using a recently installed impurity powder dropper (IPD), boron powder (μm) was injected into lower single null (LSN) L-mode discharges in WEST. IPDs possibly enable real-time wall conditioning of the plasma-facing components and may help to facilit
Autor:
George Vayakis, Y. Ma, L. B. Begrambekov, Torsten Stange, J. W. Oosterbeek, M. Hirsch, H. P. Laqua, J.-J. Cooper, Michael Walsh, I. Duran, Ph. Moreau, P. Spuig
Publikováno v:
Fusion Engineering and Design, 112, 594-612. Elsevier
Fusion Engineering and Design
Fusion Engineering and Design
High-frequency (HF) inductive magnetic sensors are the primary ITER diagnostic set for Toroidal Alfvén Eigenmodes (TAE) detection, while they also supplement low-frequency MHD and plasma equilibrium measurements. These sensors will be installed on t
Autor:
C. Reux, S. Bremond, Jérôme Bucalossi, Gérard J. Martin, Eric Nardon, S. Putvinski, Ph. Moreau, B. Vincent, T. Alarcon, F. Saint-Laurent, A. Le Luyer, P. Pastor
Publikováno v:
Fusion Engineering and Design. 89:3022-3038
Disruptions in large size tokamak like ITER must be mitigated to reduce detrimental effects on the device. Massive impurity injection prior to disruption is a promising mitigation technique. Many injector designs have already been tested on nowadays
Autor:
J.B. Lister, F. Saint-Laurent, Ph. Moreau, P. Marmillod, P. Spuig, Juan Knaster, Duccio Testa, S. Hughes, P. Pastor, Simone Peruzzo, P. Malard, George Vayakis, M. Toussaint, A. Le-Luyer, K.M. Patel
Publikováno v:
Fusion Engineering and Design. 88:1165-1169
The measurement of the plasma current in ITER plays an outstanding role as it is part of the machine protection and is a safety-relevant measurement: it will be used in relation with regulatory limits to show that the operation remains within the saf
Publikováno v:
Fusion Engineering and Design. 86:1222-1226
Fiber optic current sensors have been recently considered for current measurements in ITER. These sensors exploit Ampere's law by measuring the change of light polarization along an optical fiber subjected to a magnetic field aligned along the fiber
Autor:
J. B. Lister, R. Delogu, A. Perez, M. Toussaint, Nicolò Marconato, E. Alessi, B. Brichard, T. Maeder, L. Vermeeren, A. Gallo, René Chavan, F. Sanchez, Ph. Moreau, Y. Fournier, D. Testa, J-M Moret, Benoît Schaller, Rafael Vila, Matthias Preindl, A. Encheva, Jerome Guterl, Simone Peruzzo, A. Le-Luyer, J. Romero, G. Vayakis, Giuseppe Chitarin, E.R. Hodgson, Chris Walker, G. Tonetti, Hervé Carfantan
Publikováno v:
IEEE Transactions on Plasma Science. 38:284-294
This paper presents the multiple set of requirements for the ITER magnetic diagnostic systems and the current status of the various R&D activities performed by the EU partners.
Autor:
Sylvain Brémond, A. Geraud, Didier Mazon, P. Hertout, M. Lennholm, F. Saint-Laurent, D. Douai, Ph. Moreau
Publikováno v:
Fusion Science and Technology. 56:1284-1299
The Tore Supra tokamak is devoted to long-duration, high-performance plasma research. The real-time measurements and control (RTMC) system has been developed to address the basic tokamak controls, such as plasma equilibrium and density control. Over
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Autor:
F. Saint-Laurent, V. Basiuk, L. Ducobu, Ph. Moreau, L. Laborde, Didier Mazon, Oliviero Barana
Publikováno v:
Fusion Engineering and Design. 82:1023-1029
This work deals with the implementation and integration of advanced feedback control schemes on the Tore Supra experiment, reports the technical details and shows the first positive results that have been achieved. Encouraging outcomes have been obta
Autor:
Oliviero Barana, G. Caulier, C. Desgranges, Sylvain Brémond, J.M. Travere, F. Saint-Laurent, C. Balorin, L. Colas, F. Kazarian, Patrick Mollard, D. Guilhem, L. Millon, A. Ekedahl, R. Mitteau, Gilles Lombard, M. Jouve, Ph. Moreau, H. Roche
Publikováno v:
Fusion Engineering and Design. 82:1030-1035
Using the Tore Supra infrared thermography diagnostics, a new real time feedback control has been successfully implemented to maximize additional RF power while preventing plasma facing components (PFCs) from overheating and damage. As a first step,