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3. Conceptual design of the LHCD system on CFETR

Author

Liu, Liang, Yang, Yong, Li, Miaohui, Zhao, Lianmin, Ma, Wendong, Zhou, Tai'an, Liu, Chengzhou, Cheng, Min, Wang, Mao, Shan, Jiafang, Ding, Bojiang, Wu, Qiuran, Hillairet, Julien, Goniche, Marc, Peysson, Yves, Ekedahl, Annika, Wallace, Greg, Baek, Seung-Gyou, and Bonoli, Paul

Published
2023
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4. Multipactor in High Power Radio-Frequency Systems for Nuclear Fusion

Author

Hillairet, Julien, Goniche, Marc, Fil, Nicolas, Belhaj, Mohamed, and Puech, Jérôme

Subjects
Physics - Plasma Physics
Abstract

Magnetic confinement fusion researches are an approach to demonstrate the feasibility of nuclear fusion power for energy production. In these experiments, mega-watt range power Radio-Frequency waves, from tens of MHz to hundreds of GHz, are injected into magnetically confined plasmas in order to increase its temperature and to extend its duration. These RF systems are subjected to the magnetic field environment of the experiments, ranging from few tenth of Tesla to Tesla, and various orientations depending of their locations. As these RF systems made of copper, silver or ceramics are located in vacuum environments, they are subject to multipactor discharges. These discharges are generally considered detrimental since they can lead to detuned RF systems, limit the RF power transmission in the plasma and eventually damage RF sources or components. In some case, especially in the MHz range of frequency, multipactor discharges can be desired for vacuum conditioning. This paper presents the various RF systems used in magnetic fusion experiments and review the work performed in the fusion research community on multipactor discharges for high power coaxial (MHz) and rectangular waveguides (GHz) transmission lines, with their practical implications on power delivery into the plasma.

Published
2017

5. Ion cyclotron resonance heating systems upgrade toward high power and CW operations in WEST

Author

Hillairet, Julien, Mollard, Patrick, Zhao, Yanping, Bernard, Jean-Michel, Song, Yuntao, Argouarch, Arnaud, Berger-By, Gilles, Charabot, Nicolas, Chen, Gen, Chen, Zhaoxi, Colas, Laurent, Delaplanche, Jean-Marc, Dumortier, Pierre, Durodié, Frédéric, Ekedahl, Annika, Fedorczak, Nicolas, Ferlay, Fabien, Goniche, Marc, Hatchressian, Jean-Claude, Helou, Walid, Jacquot, Jonathan, Joffrin, Emmanuel, Litaudon, Xavier, Lombard, Gilles, Maggiora, Riccardo, Magne, Roland, Milanesio, Daniele, Patterlini, Jean-Claude, Prou, Marc, Verger, Jean-Marc, Volpe, Robert, Vulliez, Karl, Wang, Yongsheng, Winkler, Konstantin, Yang, Qingxi, and Yuan, Shuai

Subjects
Physics - Plasma Physics, Physics - Instrumentation and Detectors
Abstract

The design of the WEST (Tungsten-W Environment in Steady-state Tokamak) Ion cyclotron resonance heating antennas is based on a previously tested conjugate-T Resonant Double Loops prototype equipped with internal vacuum matching capacitors. The design and construction of three new WEST ICRH antennas are being carried out in close collaboration with ASIPP, within the framework of the Associated Laboratory in the fusion field between IRFM and ASIPP. The coupling performance to the plasma and the load-tolerance have been improved, while adding Continuous Wave operation capability by introducing water cooling in the entire antenna. On the generator side, the operation class of the high power tetrodes is changed from AB to B in order to allow high power operation (up to 3 MW per antenna) under higher VSWR (up to 2:1). Reliability of the generators is also improved by increasing the cavity breakdown voltage. The control and data acquisition system is also upgraded in order to resolve and react on fast events, such as ELMs. A new optical arc detection system comes in reinforcement of the V r /V f and SHAD systems.

Published
2016
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8. Separatrix parameters and core performances across WEST L-mode database

Author

Bourdelle, Clarisse, Morales, Jorge, Artaud, Jean François, Radenac, T., Bucalossi, Jérôme, Clairet, Frédéric, Ciraolo, Guido, Dumont, Rémi, Fedorczak, Nicolas, Gil, Christophe, Goniche, Marc, Guillemaut, Christophe, Gunn, James-Paul, Maget, Patrick, Manas, Pierre, Ostuni, Valeria, Pégourié, Bernard, Peysson, Yves, Tamain, Patrick, Vermare, L., Vezinet, Didier, Camenen, Yann, Grover, Ondrej, CEA Cadarache, Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), and The WEST Team

Subjects
[PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph]
Abstract

International audience

Published
2022

9. Characterization and integrated modelling of core radiative collapse in WEST plasmas

Author

Ostuni, Valeria, Artaud, Jean François, Bourdelle, Clarisse, Morales, Jorge, Manas, Pierre, Peysson, Yves, Fedorczak, Nicolas, Dumont, Rémi, Goniche, Marc, Maget, Patrick, icard, valerie, Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), and The WEST Team

Subjects
[PHYS]Physics [physics], ComputingMilieux_MISCELLANEOUS, [PHYS] Physics [physics]
Abstract

International audience

Published
2022

10. Developing high performance RF heating scenarios on the WEST tokamak

Author

Goniche, Marc, Bourdelle, Clarisse, Artaud, J.F., Bernard, Jean-Michel, Bucalossi, Jérôme, Colas, Laurent, Desgranges, Corinne, Léna, Delpech, Devynck, P, Bobkov, V., Gaspar, J., Klepper, C.C., Lerche, E, Shiraiwa, S., Vermare, L., Wallace, G.M., Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), max planck institute fur plasmaphysics, Aix Marseille Université (AMU), Oak Ridge National Laboratory [Oak Ridge] (ORNL), UT-Battelle, LLC, Laboratory for Plasma Physics (LPP), Ecole Royale Militaire / Koninklijke Militaire School (ERM KMS), Princeton Plasma Physics Laboratory (PPPL), Princeton University, Laboratoire de Physique des Plasmas (LPP), Observatoire de Paris, Université Paris sciences et lettres (PSL)-Université Paris sciences et lettres (PSL)-École polytechnique (X)-Sorbonne Université (SU)-Université Paris-Saclay-Centre National de la Recherche Scientifique (CNRS), M.I.T. Plasma Science and Fusion Center, and European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014)

Subjects
[PHYS]Physics [physics]
Abstract

International audience; High power experiments, up to 9.2 MW with LHCD and ICRH, have been carried out in the full tungsten tokamak WEST. Quasi non inductive discharges have been achieved allowing to extend the plasma duration to 53s at medium density (ne=3.7×10 19 m-3). Apart few pulses post-boronization, the plasma radiation is rather high (Prad/Ptot~50%) and is dominated by W. This fraction does not vary as the RF power is ramped up and, against expectations, it is quite similar in ICRH and/or LHCD heated plasmas. Hot L mode plasmas (Te(0)>3keV) with a confinement time following the ITER L96 scaling are routinely obtained, confirming the weak aspect ratio dependence of this scaling law. Tungsten accumulation is generally not an operational issue on WEST. Nonetheless, 25% of the of the discharges are affected by a rapid collapse of the central electron temperature which occurs when a slight decrease of Te leads to enhanced radiation causing flat or hollow current profiles. To this respect LHCD-only discharges are compared to ICRH and ICRH/LHCD discharges.

Published
2021

11. SOL RF physics modelling in Europe, in support of ICRF experiments

Author

Colas Laurent, Lu LingFeng, Jacquot Jonathan, Tierens Wouter, Křivská Alena, Heuraux Stéphane, Faudot Eric, Tamain Patrick, Després Bruno, Van Eester Dirk, Crombé Kristel, Louche Fabrice, Hillairet Julien, Helou Walid, and Goniche Marc

Subjects
Physics, QC1-999
Abstract

A European project was undertaken to improve the available SOL ICRF physics simulation tools and confront them with measurements. This paper first reviews code upgrades within the project. Using the multi-physics finite element solver COMSOL, the SSWICH code couples RF full-wave propagation with DC plasma biasing over “antenna-scale” 2D (toroidal/radial) domains, via non-linear RF and DC sheath boundary conditions (SBCs) applied at shaped plasma-facing boundaries. For the different modules and associated SBCs, more elaborate basic research in RF-sheath physics, SOL turbulent transport and applied mathematics, generally over smaller spatial scales, guides code improvement. The available simulation tools were applied to interpret experimental observations on various tokamaks. We focus on robust qualitative results common to several devices: the spatial distribution of RF-induced DC bias; left-right asymmetries over strap power unbalance; parametric dependence and antenna electrical tuning; DC SOL biasing far from the antennas, and RF-induced density modifications. From these results we try to identify the relevant physical ingredients necessary to reproduce the measurements, e.g. accurate radiated field maps from 3D antenna codes, spatial proximity effects from wave evanescence in the near RF field, or DC current transport. Pending issues towards quantitative predictions are also outlined.

Published
2017
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12. Influence of Li conditioning on Lower Hybrid Current Drive efficiency in H-mode and L- mode plasmas on EAST

Author

Goniche Marc, Li Miaohui, Peysson Yves, Chen Yingjie, Ding Bojiang, Ekedahl Annika, Liu Haiqing, Liu Yong, Qian Jinping, Yang Xiuda, Zang Qing, Zhang Tao, Zhen Sun, and Zou Xiao-Lan

Subjects
Physics, QC1-999
Abstract

The lower hybrid current drive efficiency on the EAST tokamak is estimated on a large database of low loop voltage discharges (VL of these discharges, can account for the high efficiency according to the expected scaling with Zeff and . Modelling with a ray-tracing code coupled to a Fokker-Planck solver supports this result, assuming that the fast electron transport is reduced in the zero loop voltage discharge with high efficiency.

Published
2017
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13. The Role of the Plasma Current in Turbulence Decrease with Lower Hybrid Waves

Author

Antar Ghassan, Goniche Marc, and Ekedahl Annika

Subjects
Physics, QC1-999
Abstract

We study the effect of lower hybrid waves on edge turbulence using a set of two Langmuir probes inserted in the scrape-off layer of the Tore Supra tokamak. We use the cross-correlation coefficient to assess the interplay between turbulence and the LH waves. We found that turbulence is affected at high plasma current even at relatively low LH powers. When the plasma current is below 1 MA, this effect disappears. Finally, we show that the level of fluctuations and the cross-correlation amplitude are correlated whereas the increase of the first leads to the increase of the second. The role of the plasma current could reflect that the exchange of the RF waves with edge turbulence is occurring in the closed field lines rather in the open field lines range.

Published
2017
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14. Lower hybrid current drive experiments in support of high confinement long pulse operation in EAST

Author

Ekedahl Annika, Ding Bojiang, Gong Xianzu, Goniche Marc, Li Miaohui, Peysson Yves, Qian Jinping, Hillairet Julien, Hoang Tuong, Liu Fukun, Qin Chengming, Song Yuantao, Wang Xiaojie, Zhang Xinjun, Zhao Yanping, and Zou Xiao-Lan

Subjects
Physics, QC1-999
Abstract

The lower hybrid current drive (LHCD) system plays a crucial role in the mission of the Experimental Advanced Superconducting Tokamak (EAST) and is a prerequisite for reaching long pulse, high confinement plasmas on EAST [1, 2]. LHCD experiments and modelling [3] have been carried out on EAST in 2015-2016, with the aim to optimising EAST long pulse scenarios, and at the same time gain experience for the exploitation of WEST [4]. Experiments have been carried out to study the LH current drive efficiency in different plasma configurations (Upper Single Null and Lower Single Null). The effect of the gas feed location on the LH wave coupling was investigated by comparing gas fuelling from high field side, low field side and upper divertor. In view of long pulse H-mode scenarios, a series of H-mode experiments were conducted where all the heating power was provided by RF heating methods only, i.e. LHCD, ECRH and ICRH. H-modes were sustained in both Upper Single Null (W divertor) and Lower Single Null (carbon divertor) configurations, with loop voltage maintained as low as 50 mV.

Published
2017
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15. Recent H majority inverted radio frequency heating scheme experiments in JET-ILW

Author

Van Eester Dirk, Lerche Ernesto, Kazakov Yevgen, Jacquet Philippe, Baranov Yuri, Bobkov Volodymyr, Crombé Kristel, Czarnecka Agata, Dumont Remi, Dumortier Pierre, Eriksson Jacob, Giacomelli Luca, Giroud Carine, Goniche Marc, Hellesen Carl, Kiptily Vasily, Krawczyk Natalia, Koskela Tuomas, Nave Filomena, Nocente Massimo, Ongena Jef, Santala Marko, Salewski Mirko, Schneider Mireille, and Weisen Henri

Subjects
Physics, QC1-999
Abstract

Inverted 3He and D ion cyclotron minority heating scenarios were recently tested in JET-ILW. They confirm the good heating efficiency at low concentrations of ∼3%. The 3He minority heating scheme is only modestly affected by the change from a carbon (JET-C) to a Beryllium (JET-ILW) wall but unlike what was the case in JET-C, the intrinsic Be ions D-like particles in terms of charge-over-mass ratio do not prevent the D (or 4He) minority regime from being exploited. Direct and indirect evidence of the existence of fast particle subpopulations was found in both cases.

Published
2017
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16. Modelling of combined ICRF and NBI heating in JET hybrid plasmas

Author

Gallart Dani, Mantsinen Mervi, Challis Clive, Frigione Domenico, Graves Jonathan, Hobirk Joerg, Belonohy Eva, Czarnecka Agata, Eriksson Jacob, Goniche Marc, Hellesen Carl, Jacquet Philippe, Joffrin Emmanuel, Krawczyk Natalia, King Damian, Lennholm Morten, Lerche Ernesto, Pawelec Ewa, Sips George, Solano Emilia, Tsalas Maximos, and Valisa Marco

Subjects
Physics, QC1-999
Abstract

During the 2015-2016 JET campaigns many efforts have been devoted to the exploration of high performance plasma scenarios envisaged for ITER operation. In this paper we model the combined ICRF+NBI heating in selected key hybrid discharges using PION. The antenna frequency was tuned to match the cyclotron frequency of minority hydrogen (H) at the center of the tokamak coinciding with the second harmonic cyclotron resonance of deuterium. The modelling takes into account the synergy between ICRF and NBI heating through the second harmonic cyclotron resonance of deuterium beam ions which allows us to assess its impact on the neutron rate RNT. We evaluate the influence of H concentration which was varied in different discharges in order to test their role in the heating performance. According to our modelling, the ICRF enhancement of RNT increases by decreasing the H concentration which increases the ICRF power absorbed by deuterons. We find that in the recent hybrid discharges this ICRF enhancement was in the range of 10-25%. Finally, we extrapolate the results to D-T and find that the best performing hybrid discharges correspond to an equivalent fusion power of ∼7.0 MW in D-T.

Published
2017
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17. The Role of Combined ICRF and NBI Heating in JET Hybrid Plasmas in Quest for High D-T Fusion Yield

Author

Mantsinen Mervi, Challis Clive, Frigione Domenico, Graves Jonathan, Hobirk Joerg, Belonohy Eva, Czarnecka Agata, Eriksson Jacob, Gallart Dani, Goniche Marc, Hellesen Carl, Jacquet Philippe, Joffrin Emmanuel, King Damian, Krawczyk Natalia, Lennholm Morten, Lerche Ernesto, Pawelec Ewa, Sips George, Solano Emilia R., Tsalas Maximos, and Valisa Marco

Subjects
Physics, QC1-999
Abstract

Combined ICRF and NBI heating played a key role in achieving the world-record fusion yield in the first deuterium-tritium campaign at the JET tokamak in 1997. The current plans for JET include new experiments with deuterium-tritium (D-T) plasmas with more ITER-like conditions given the recently installed ITER-like wall (ILW). In the 2015-2016 campaigns, significant efforts have been devoted to the development of high-performance plasma scenarios compatible with ILW in preparation of the forthcoming D-T campaign. Good progress was made in both the inductive (baseline) and the hybrid scenario: a new record JET ILW fusion yield with a significantly extended duration of the high-performance phase was achieved. This paper reports on the progress with the hybrid scenario which is a candidate for ITER longpulse operation (∼1000 s) thanks to its improved normalized confinement, reduced plasma current and higher plasma beta with respect to the ITER reference baseline scenario. The combined NBI+ICRF power in the hybrid scenario was increased to 33 MW and the record fusion yield, averaged over 100 ms, to 2.9x1016 neutrons/s from the 2014 ILW fusion record of 2.3x1016 neutrons/s. Impurity control with ICRF waves was one of the key means for extending the duration of the high-performance phase. The main results are reviewed covering both key core and edge plasma issues.

Published
2017
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18. Formation of the radial electric field profile in WEST tokamak

Author

Vermare, Laure, Dif-Pradalier, Guilhem, Hennequin, Pascale, Gunn, James, Garbet, Xavier, Artaud, Jean-Francois, Gurcan, Ozgur, Bourdelle, Clarisse, Clairet, Frédéric, Fedorczak, Nicolas, Honoré, Cyrille, Morales, Jorge, Sarazin, Yanick, Grandgirard, Virginie, Varennes, Robin, Vezinet, Didier, Peret, Mathieu, Dumont, Rémi, Goniche, Marc, Maget, Patrick, icard, valerie, Implementation of activities described in the Roadmap to Fusion during Horizon 2020 through a Joint programme of the members of the EUROfusion consortium - EUROfusion - - H20202014-01-01 - 2018-12-31 - 633053 - VALID, Laboratoire de Physique des Plasmas (LPP), Observatoire de Paris, Université Paris sciences et lettres (PSL)-Université Paris sciences et lettres (PSL)-École polytechnique (X)-Sorbonne Université (SU)-Université Paris-Saclay-Centre National de la Recherche Scientifique (CNRS), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), The WEST Team, and European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014)

Subjects
[PHYS]Physics [physics], [PHYS] Physics [physics]
Abstract

International audience; The shear of the radial electric field at the edge is widely accepted to be responsible for turbulence reductionin edge transport barriers and thought as a key ingredient of the improved confinement of H-mode plasmas.Nevertheless, a full understanding of how its profile builds up at the edge is still lacking. It can either beformulated as the result of a competition between several mechanisms that generate and damp flows or as theresult of a non-ambipolar particle flux, which enhances radial charge separation imposing a radial electric fieldprofile. Among possible mechanisms, one can think of turbulence generated flow via Reynolds stress, ion orbitlosses, toroidal magnetic ripple and the effect of neutral friction at the edge. Based on previous results obtainedon Tore Supra, the radial profile of the perpendicular flow expected in WEST can be separated in three spatialareas. Inside ρ = 0.8, the radial electric field is dominated by losses of thermal ions in the magnetic ripple while between 0.7 < ρ < 0.95, a competition between this latter and the generation of large scale flows byturbulence appears as a possible explanation of the measured poloidal asymmetry of the mean perpendicularvelocity. In addition, edge conditions such as contact points and parallel dynamics in the scrape-off-layer(SOL) influence the edge profiles beyond ρ = 0.9 (3). This contribution presents unexpected differences in theradial electric field profile observed in WEST between Lower Single Null (LSN) and Upper Single Null (USN)configurations and a study of the competition between specific mechanisms playing a role in the formationof this profile.

Published
2021

20. Recent H majority inverted radio frequency heating scheme experiments in JET-ILW

Author

Van Eester, D, Lerche, E, Kazakov, Y, Jacquet, P, Baranov, Y, Bobkov, V, Crombã©, K, Czarnecka, A, Dumont, R, Dumortier, P, Eriksson, J, Giacomelli, L, Giroud, C, Goniche, M, Hellesen, C, Kiptily, V, Krawczyk, N, Koskela, T, Nave, F, Nocente, M, Ongena, J, Santala, M, Salewski, M, Schneider, M, Weisen, H, Van Eester, Dirk, Lerche, Ernesto, Kazakov, Yevgen, Jacquet, Philippe, Baranov, Yuri, Bobkov, Volodymyr, Crombé, Kristel, Czarnecka, Agata, Dumont, Remi, Dumortier, Pierre, Eriksson, Jacob, Giacomelli, Luca, Giroud, Carine, Goniche, Marc, Hellesen, Carl, Kiptily, Vasily, Krawczyk, Natalia, Koskela, Tuomas, Nave, Filomena, Nocente, Massimo, Ongena, Jef, Santala, Marko, Salewski, Mirko, Schneider, Mireille, Weisen, Henri, Van Eester, D, Lerche, E, Kazakov, Y, Jacquet, P, Baranov, Y, Bobkov, V, Crombã©, K, Czarnecka, A, Dumont, R, Dumortier, P, Eriksson, J, Giacomelli, L, Giroud, C, Goniche, M, Hellesen, C, Kiptily, V, Krawczyk, N, Koskela, T, Nave, F, Nocente, M, Ongena, J, Santala, M, Salewski, M, Schneider, M, Weisen, H, Van Eester, Dirk, Lerche, Ernesto, Kazakov, Yevgen, Jacquet, Philippe, Baranov, Yuri, Bobkov, Volodymyr, Crombé, Kristel, Czarnecka, Agata, Dumont, Remi, Dumortier, Pierre, Eriksson, Jacob, Giacomelli, Luca, Giroud, Carine, Goniche, Marc, Hellesen, Carl, Kiptily, Vasily, Krawczyk, Natalia, Koskela, Tuomas, Nave, Filomena, Nocente, Massimo, Ongena, Jef, Santala, Marko, Salewski, Mirko, Schneider, Mireille, and Weisen, Henri

Abstract

Inverted3He and D ion cyclotron minority heating scenarios were recently tested in JET-ILW. They confirm the good heating efficiency at low concentrations of ∼3%. The3He minority heating scheme is only modestly affected by the change from a carbon (JET-C) to a Beryllium (JET-ILW) wall but unlike what was the case in JET-C, the intrinsic Be ions D-like particles in terms of charge-over-mass ratio do not prevent the D (or4He) minority regime from being exploited. Direct and indirect evidence of the existence of fast particle subpopulations was found in both cases

Published
2017

21. The Role of Combined ICRF and NBI Heating in JET Hybrid Plasmas in Quest for High D-T Fusion Yield

Author

Barcelona Supercomputing Center, Mantsinen, Mervi, Challis, Clive, Frigione, Domenico, Graves, Jonathan, Hobirk, Joerg, Belonohy, Eva, Czarnecka, Agata, Eriksson, Jacob, Gallart, Dani, Goniche, Marc, Hellesen, Carl, Jacquet, Philippe, Joffrin, Emmanuel, King, Damian, Krawczyk, Natalia, Lennholm, Morten, Lerche, Ernesto, Pawelec, Ewa, Sips, George, Solano, Emilia R., Tsalas, Maximos, Valisa, Marco, JET Contributors, Barcelona Supercomputing Center, Mantsinen, Mervi, Challis, Clive, Frigione, Domenico, Graves, Jonathan, Hobirk, Joerg, Belonohy, Eva, Czarnecka, Agata, Eriksson, Jacob, Gallart, Dani, Goniche, Marc, Hellesen, Carl, Jacquet, Philippe, Joffrin, Emmanuel, King, Damian, Krawczyk, Natalia, Lennholm, Morten, Lerche, Ernesto, Pawelec, Ewa, Sips, George, Solano, Emilia R., Tsalas, Maximos, Valisa, Marco, and JET Contributors

Abstract

Combined ICRF and NBI heating played a key role in achieving the world-record fusion yield in the first deuterium-tritium campaign at the JET tokamak in 1997. The current plans for JET include new experiments with deuterium-tritium (D-T) plasmas with more ITER-like conditions given the recently installed ITER-like wall (ILW). In the 2015-2016 campaigns, significant efforts have been devoted to the development of high-performance plasma scenarios compatible with ILW in preparation of the forthcoming D-T campaign. Good progress was made in both the inductive (baseline) and the hybrid scenario: a new record JET ILW fusion yield with a significantly extended duration of the high-performance phase was achieved. This paper reports on the progress with the hybrid scenario which is a candidate for ITER longpulse operation (∼1000 s) thanks to its improved normalized confinement, reduced plasma current and higher plasma beta with respect to the ITER reference baseline scenario. The combined NBI+ICRF power in the hybrid scenario was increased to 33 MW and the record fusion yield, averaged over 100 ms, to 2.9x1016 neutrons/s from the 2014 ILW fusion record of 2.3x1016 neutrons/s. Impurity control with ICRF waves was one of the key means for extending the duration of the high-performance phase. The main results are reviewed covering both key core and edge plasma issues., This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission., Peer Reviewed, Postprint (published version)

Published
2017

22. Modelling of combined ICRF and NBI heating in JET hybrid plasmas

Author

Barcelona Supercomputing Center, Gallart, Dani, Mantsinen, Mervi, Challis, Clive, Frigione, Domenico, Graves, Jonathan, Hobirk, Joerg, Belonohy, Eva, Czarnecka, Agata, Eriksson, Jacob, Goniche, Marc, Hellesen, Carl, Jacquet, Philippe, Joffrin, Emmanuel, Krawczyk, Natalia, King, Damian, Lennholm, Morten, Lerche, Ernesto, Pawelec, Ewa, Sips, George, Solano, Emilia, Tsalas, Maximos, Valisa, Marco, JET Contributors, Barcelona Supercomputing Center, Gallart, Dani, Mantsinen, Mervi, Challis, Clive, Frigione, Domenico, Graves, Jonathan, Hobirk, Joerg, Belonohy, Eva, Czarnecka, Agata, Eriksson, Jacob, Goniche, Marc, Hellesen, Carl, Jacquet, Philippe, Joffrin, Emmanuel, Krawczyk, Natalia, King, Damian, Lennholm, Morten, Lerche, Ernesto, Pawelec, Ewa, Sips, George, Solano, Emilia, Tsalas, Maximos, Valisa, Marco, and JET Contributors

Abstract

During the 2015-2016 JET campaigns many efforts have been devoted to the exploration of high performance plasma scenarios envisaged for ITER operation. In this paper we model the combined ICRF+NBI heating in selected key hybrid discharges using PION. The antenna frequency was tuned to match the cyclotron frequency of minority hydrogen (H) at the center of the tokamak coinciding with the second harmonic cyclotron resonance of deuterium. The modelling takes into account the synergy between ICRF and NBI heating through the second harmonic cyclotron resonance of deuterium beam ions which allows us to assess its impact on the neutron rate RNT. We evaluate the influence of H concentration which was varied in different discharges in order to test their role in the heating performance. According to our modelling, the ICRF enhancement of RNT increases by decreasing the H concentration which increases the ICRF power absorbed by deuterons. We find that in the recent hybrid discharges this ICRF enhancement was in the range of 10-25%. Finally, we extrapolate the results to D-T and find that the best performing hybrid discharges correspond to an equivalent fusion power of ∼7.0 MW in D-T., This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. Dani Gallart would like to thank “La Caixa” for support of his PhD studies., Peer Reviewed, Postprint (published version)

Published
2017

23. Recent H majority inverted radio frequency heating scheme experiments in JET-ILW

Author

Van Eester, Dirk, Lerche, Ernesto, Kazakov, Yevgen, Jacquet, Philippe, Baranov, Yuri, Bobkov, Volodymyr, Crombé, Kristel, Czarnecka, Agata, Dumont, Remi, Dumortier, Pierre, Eriksson, Jacob, Giacomelli, Luca, Giroud, Carine, Goniche, Marc, Hellesen, Carl, Kiptily, Vasily, Krawczyk, Natalia, Koskela, Tuomas, Nave, Filomena, Nocente, Massimo, Ongena, Jef, Santala, Marko, Salewski, Mirko, Schneider, Mireille, Weisen, Henri, Hillairet, J., Van Eester, Dirk, Lerche, Ernesto, Kazakov, Yevgen, Jacquet, Philippe, Baranov, Yuri, Bobkov, Volodymyr, Crombé, Kristel, Czarnecka, Agata, Dumont, Remi, Dumortier, Pierre, Eriksson, Jacob, Giacomelli, Luca, Giroud, Carine, Goniche, Marc, Hellesen, Carl, Kiptily, Vasily, Krawczyk, Natalia, Koskela, Tuomas, Nave, Filomena, Nocente, Massimo, Ongena, Jef, Santala, Marko, Salewski, Mirko, Schneider, Mireille, Weisen, Henri, and Hillairet, J.

Abstract

Inverted 3He and D ion cyclotron minority heating scenarios were recently tested in JET-ILW. They confirm the good heating efficiency at low concentrations of ~3%. The 3He minority heating scheme is only modestly affected by the change from a carbon (JET-C) to a Beryllium (JET-ILW) wall but unlike what was the case in JET-C, the intrinsic Be ions D-like particles in terms of charge-over-mass ratio do not prevent the D (or 4He) minority regime from being exploited. Direct and indirect evidence of the existence of fast particle subpopulations was found in both cases.

Published
2017

25. An Optimal Feedback Approach to Particle Source Identification in Tokamaks

Author

Santiago, Enrique, Witrant, Emmanuel, Goniche, Marc, Clairet, F., GIPSA - Systèmes linéaires et robustesse (GIPSA-SLR), Département Automatique (GIPSA-DA), Grenoble Images Parole Signal Automatique (GIPSA-lab), Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Stendhal - Grenoble 3-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Stendhal - Grenoble 3-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Grenoble Images Parole Signal Automatique (GIPSA-lab), Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Stendhal - Grenoble 3-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Stendhal - Grenoble 3-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Université Stendhal - Grenoble 3-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Université Stendhal - Grenoble 3-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Grenoble Images Parole Signal Automatique (GIPSA-lab), Université Stendhal - Grenoble 3-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Université Stendhal - Grenoble 3-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS), and Witrant, Emmanuel

Subjects
[SPI.AUTO] Engineering Sciences [physics]/Automatic, Physics::Plasma Physics, [PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], [PHYS.PHYS.PHYS-PLASM-PH] Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], [SPI.AUTO]Engineering Sciences [physics]/Automatic
Abstract

International audience; A new identification technique is proposed to study the plasma phenomena taking place in the so-called \emph{scrape-off layer} and their correlation with the \emph{lower hybrid} radio frequency antenna in the experimental nuclear fusion tokamak reactor \emph{Tore Supra}. A deeper knowledge of the plasma behavior in this region would contribute to the achievement of steady-state controlled thermonuclear fusion for power generation. The proposed approach relies on the design of a feedback/feedforward optimized architecture to solve a blind identification problem. While our paper is mostly focused on experimental results for the studied application, it can provide valuable insights on input estimation and model validation for transport phenomena described by partial differential equations.

Published
2011

26. Excitation d'un milieu plasma par une antenne

Author

Ben Hsouna, Mohamed Nabil, Thevenot, Marc, Carsenat, David, Monédière, Thierry, Goniche, Marc, OSA (XLIM-OSA), XLIM (XLIM), Université de Limoges (UNILIM)-Centre National de la Recherche Scientifique (CNRS)-Université de Limoges (UNILIM)-Centre National de la Recherche Scientifique (CNRS), OSA, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), and Commissariat à l'énergie atomique et aux énergies alternatives (CEA)

Subjects
ComputingMilieux_MISCELLANEOUS
Abstract

National audience

Published
2011

27. Radio-frequency electrical design of the WEST long pulse and load-resilient ICRH launchers

Author

Helou, Walid, primary, Colas, Laurent, additional, Hillairet, Julien, additional, Milanesio, Daniele, additional, Mollard, Patrick, additional, Argouarch, Arnaud, additional, Berger-By, Gilles, additional, Bernard, Jean-Michel, additional, Chen, Zhaoxi, additional, Delaplanche, Jean-Marc, additional, Dumortier, Pierre, additional, Durodié, Frédéric, additional, Ekedahl, Annika, additional, Fedorczak, Nicolas, additional, Ferlay, Fabien, additional, Goniche, Marc, additional, Jacquot, Jonathan, additional, Joffrin, Emmanuel, additional, Litaudon, Xavier, additional, Lombard, Gilles, additional, Maggiora, Riccardo, additional, Magne, Roland, additional, Patterlini, Jean-Claude, additional, Prou, Marc, additional, Volpe, Robert, additional, Vulliez, Karl, additional, and Winkler, Konstantin, additional

Published
2015
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28. Evolution of the Tore Supra Lower Hybrid Current Drive System for WEST

Author

Delpech, Léna, primary, Achard, Joelle, additional, Armitano, Arthur, additional, Berger-By, Gilles, additional, Ekedahl, Annika, additional, Gargiulo, Laurent, additional, Goniche, Marc, additional, Guilhem, Dominique, additional, Hertout, Patrick, additional, Hillairet, Julien, additional, Magne, Roland, additional, Mollard, Patrick, additional, Piluso, P., additional, Poli, Serge, additional, Prou, Marc, additional, Saille, Alain, additional, and Samaille, Franck, additional

Published
2015
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31. Ion cyclotron resonance heating systems upgrade toward high power and CW operations in WEST

Author

Hillairet, Julien, primary, Mollard, Patrick, additional, Zhao, Yanping, additional, Bernard, Jean-Michel, additional, Song, Yuntao, additional, Argouarch, Arnaud, additional, Berger-By, Gilles, additional, Charabot, Nicolas, additional, Chen, Gen, additional, Chen, Zhaoxi, additional, Colas, Laurent, additional, Delaplanche, Jean-Marc, additional, Dumortier, Pierre, additional, Durodié, Frédéric, additional, Ekedahl, Annika, additional, Fedorczak, Nicolas, additional, Ferlay, Fabien, additional, Goniche, Marc, additional, Hatchressian, Jean-Claude, additional, Helou, Walid, additional, Jacquot, Jonathan, additional, Joffrin, Emmanuel, additional, Litaudon, Xavier, additional, Lombard, Gilles, additional, Maggiora, Riccardo, additional, Magne, Roland, additional, Milanesio, Daniele, additional, Patterlini, Jean-Claude, additional, Prou, Marc, additional, Verger, Jean-Marc, additional, Volpe, Robert, additional, Vulliez, Karl, additional, Wang, Yongsheng, additional, Winkler, Konstantin, additional, Yang, Qingxi, additional, and Yuan, Shuai, additional

Published
2015
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32. SIDON: A simulator of radio-frequency networks. Application to WEST ICRF launchers

Author

Helou, Walid, primary, Dumortier, Pierre, additional, Durodié, Frédéric, additional, Goniche, Marc, additional, Hillairet, Julien, additional, Mollard, Patrick, additional, Berger-By, Gilles, additional, Bernard, Jean-Michel, additional, Colas, Laurent, additional, Lombard, Gilles, additional, Maggiora, Riccardo, additional, Magne, Roland, additional, Milanesio, Daniele, additional, and Moreau, Didier, additional

Published
2015
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33. A QSS approach for particle source identification in Tore Supra tokamak

Author

Witrant, Emmanuel, Goniche, Marc, GIPSA - Systèmes linéaires et robustesse (GIPSA-SLR), Département Automatique (GIPSA-DA), Grenoble Images Parole Signal Automatique (GIPSA-lab), Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Stendhal - Grenoble 3-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Stendhal - Grenoble 3-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Grenoble Images Parole Signal Automatique (GIPSA-lab), Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Stendhal - Grenoble 3-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Stendhal - Grenoble 3-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Université Stendhal - Grenoble 3-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Université Stendhal - Grenoble 3-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Grenoble Images Parole Signal Automatique (GIPSA-lab), Université Stendhal - Grenoble 3-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Université Stendhal - Grenoble 3-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS), and Witrant, Emmanuel

Subjects
[SPI.AUTO] Engineering Sciences [physics]/Automatic, Physics::Plasma Physics, [PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], [PHYS.PHYS.PHYS-PLASM-PH] Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], [SPI.AUTO]Engineering Sciences [physics]/Automatic
Abstract

International audience; In this work, we consider the problem of particle source identification from distributed electron density measurements in fusion plasmas, such as the ones obtained in Tore Supra tokamak. A transport model, suitable for identification purposes, is first proposed based on a simplification of classical particle transport models. We then derive a quasi-steady state (QSS) description, which is shown to converge exponentially towards the true solution. Finally, an identification method is proposed based on the QSS model and a shape approximation of the source term. ToreSupra data is used to illustrate the different results with experimental measurements.

Published
2009

34. Optimal estimation of the particle sources in Tore Supra tokamak

Author

Weydert, Jacques, Witrant, Emmanuel, Goniche, Marc, GIPSA - Systèmes linéaires et robustesse (GIPSA-SLR), Département Automatique (GIPSA-DA), Grenoble Images Parole Signal Automatique (GIPSA-lab), Université Stendhal - Grenoble 3-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Université Stendhal - Grenoble 3-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Grenoble Images Parole Signal Automatique (GIPSA-lab), Université Stendhal - Grenoble 3-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Université Stendhal - Grenoble 3-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Witrant, Emmanuel, Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Stendhal - Grenoble 3-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Stendhal - Grenoble 3-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Grenoble Images Parole Signal Automatique (GIPSA-lab), and Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Stendhal - Grenoble 3-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Stendhal - Grenoble 3-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)

Subjects
[SPI.AUTO] Engineering Sciences [physics]/Automatic, [PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], [PHYS.PHYS.PHYS-PLASM-PH] Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], ComputingMilieux_MISCELLANEOUS, [SPI.AUTO]Engineering Sciences [physics]/Automatic
Abstract

International audience

Published
2009

35. Toward particle source identification in Tore Supra tokamak

Author

Witrant, Emmanuel, Weydert, Jacques, Goniche, Marc, Clairet, F., GIPSA - Systèmes linéaires et robustesse (GIPSA-SLR), Département Automatique (GIPSA-DA), Grenoble Images Parole Signal Automatique (GIPSA-lab), Université Stendhal - Grenoble 3-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Université Stendhal - Grenoble 3-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Grenoble Images Parole Signal Automatique (GIPSA-lab), Université Stendhal - Grenoble 3-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Université Stendhal - Grenoble 3-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Association EURATOM-CEA (CEA/DSM/DRFC), Witrant, Emmanuel, Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Stendhal - Grenoble 3-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Stendhal - Grenoble 3-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Grenoble Images Parole Signal Automatique (GIPSA-lab), and Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Stendhal - Grenoble 3-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)-Université Pierre Mendès France - Grenoble 2 (UPMF)-Université Stendhal - Grenoble 3-Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Centre National de la Recherche Scientifique (CNRS)

Subjects
[SPI.AUTO] Engineering Sciences [physics]/Automatic, [PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], [PHYS.PHYS.PHYS-PLASM-PH] Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], ComputingMilieux_MISCELLANEOUS, [SPI.AUTO]Engineering Sciences [physics]/Automatic
Abstract

International audience

Published
2009

36. Development of Long Pulse RF Heating and Current Drive for H-Mode Scenarios with Metallic Walls in WEST.

Author

Ekedahl, Annika, Bourdelle, Clarisse, Artaud, Jean-François, Bernard, Jean-Michel, Bufferand, Hugo, Colas, Laurent, Decker, Joan, Delpech, Léna, Dumont, Rémi, Goniche, Marc, Helou, Walid, Hillairet, Julien, Lombard, Gilles, Magne, Roland, Mollard, Patrick, Nardon, Eric, Peysson, Yves, and Tsitrone, Emmanuelle

Subjects
RADIOFREQUENCY heating, CURRENT-drive heating, TOKAMAKS, STEADY-state flow, HEAT flux
Abstract

The longstanding expertise of the Tore Supra team in long pulse heating and current drive with radiofrequency (RF) systems will now be exploited in the WEST device (tungsten-W Environment in Steady-state Tokamak) [1]. WEST will allow an integrated long pulse tokamak programme for testing W-divertor components at ITER-relevant heat flux (10-20 MW/m²), while treating crucial aspects for ITER-operation, such as avoidance of W-accumulation in long discharges, monitoring and control of heat fluxes on the metallic plasma facing components (PFCs) and coupling of RF waves in H-mode plasmas. Scenario modelling using the METIS-code shows that ITER-relevant heat fluxes are compatible with the sustainment of long pulse H-mode discharges, at high power (up to 15 MW / 30 s at IP = 0.8 MA) or high fluence (up to 10 MW / 1000 s at IP = 0.6 MA) [2], all based on RF heating and current drive using Ion Cyclotron Resonance Heating (ICRH) and Lower Hybrid Current Drive (LHCD). This paper gives a description of the ICRH and LHCD systems in WEST, together with the modelling of the power deposition of the RF waves in the WEST-scenarios. [ABSTRACT FROM AUTHOR]

Published
2015
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37. Positive plasma biaising in front of the lower hybrid grill of CASTOR tokamak

Author

Zacek, Frantisek, Petrzilka, Vaclav, Adamek, Jiri, Goniche, Marc, Devynck, Pascal, Association Euratom/IPP.CR, Czech Academy of Sciences [Prague] (ASCR), Service de réanimation médicale, Assistance publique - Hôpitaux de Paris (AP-HP) (APHP)-Université Paris Diderot - Paris 7 (UPD7)-Groupe Hospitalier Saint Louis - Lariboisière - Fernand Widal [Paris], Assistance publique - Hôpitaux de Paris (AP-HP) (APHP), Czech Academy of Sciences [Prague] (CAS), Université Paris Diderot - Paris 7 (UPD7)-Groupe Hospitalier Saint Louis - Lariboisière - Fernand Widal [Paris], Assistance publique - Hôpitaux de Paris (AP-HP) (AP-HP)-Assistance publique - Hôpitaux de Paris (AP-HP) (AP-HP), and Zacek, Frantisek

Subjects
Physics::Plasma Physics, particle acceleration, wall erosion, emissive Langmuir probe, [PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], [PHYS.PHYS.PHYS-PLASM-PH] Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph], lower hybrid, 52.25, tokamak
Abstract

12th International Congress on Plasma Physics, 25-29 October 2004, Nice (France); Parasitic generation of suprathermal particles in front of lower hybrid (LH) antennas in tokamaks represents a serious danger for the parts of tokamak first wall connected with this region directly by magnetic field lines. Presence of electrons in radially very narrow wave-plasma interaction region, accelerated up to the energy 200eV, has been proved recently on CASTOR tokamak by Langmuir probes (a substantial drop of floating potential is observed). Using emissive Langmuir probes, first experimental evidence of increase of plasma potential in the interaction region is given in this paper. This result confirms predictions of theory about the charge separation due to the escape of accelerated electrons with successive acceleration of plasma ions.

Published
2004

39. Implications of the Tore-Supra WEST-Project on Radio-Frequency Additionnal Heating Systems

Author

Guilhem, Dominique, primary, Argouarch, Arnaud, additional, Bernard, Jean-Michel, additional, Bouquey, Francis, additional, Colas, Laurent, additional, Delpech, Lena, additional, Durodie, Frederic, additional, Ekedahl, Annika, additional, Van Helvoirt, Jan, additional, Hillairet, Julien, additional, Joffrin, Emmanuel, additional, Litaudon, Xavier, additional, Magne, Roland, additional, Milanesio, Daniele, additional, Moerel, Jean, additional, Mollard, Patrick, additional, Wittebol, Erik, additional, Achard, Joelle, additional, Armitano, Arthur, additional, Berger-By, Gilles, additional, Charabot, Nicolas, additional, Goniche, Marc, additional, Jacquot, Jonathan, additional, Lombard, Gilles, additional, Prou, Marc, additional, Traisnel-Corbel, Elodie, additional, Volpe, Robert, additional, and Vulliez, Karl, additional

Published
2014
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41. Radio-Frequency Sheaths Physics: Experimental Characterization on Tore Supra and Related Self-Consistent Modeling.

Author

Jacquot, Jonathan, Milanesio, Daniele, Colas, Laurent, Corre, Yann, Goniche, Marc, Gunn, Jamie, Heuraux, Stéphane, and Kubic, Martin

Subjects
RADIO frequency, PLASMA sheaths, FARADAY cage, ICR heating, HEAT flux, ANTENNAS in plasma, CANTILEVERS, TOKAMAKS
Abstract

During the 2011 experimental campaign, one of the three ion cyclotron resonance heating (ICRH) antennas in the Tore Supra (TS) tokamak was equipped with a new type of Faraday screen (FS). The new design aimed at minimizing RF sheaths as well as increasing the heat exhaust capability of the actively cooled screen. It proved to be inefficient for attenuating the RF-sheaths on the screen itself on the contrary to the heat exhaust concept that allowed operation despite higher heat fluxes on the antenna. In parallel, a new approach has been proposed to model self-consistently RF sheaths: the SSWICH (Self-consistent Sheaths and Waves for IC Heating) code. Simulations results from SSWICH coupled with the TOPICA antenna code were able to reproduce the difference between the two FS designs and part of the spatial pattern of heat loads and floating potential. The poloidal pattern is a reliable result that mainly depends on the electrical design of the antenna while the radial pattern is on the contrary highly sensitive to loosely constrained parameters such as perpendicular conductivity that generates a DC current circulation from the the private region inside the antenna limiters to the free SOL outside these limiters. Moreover the cantilevered bars seem to be the element in the design of the new screen that enhanced RF sheaths. [ABSTRACT FROM AUTHOR]

Published
2014
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