75 results on '"icard, valerie"'
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2. First wall fluxes in ITER from full vessel edge-plasma simulations
- Author
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Rivals, Nicolas, P., Tamain, Y., Marandet, X., Bonnin, H., Bufferand, R.A., Pitts, G., Falchetto, Yang, H., G., Ciraolo, CEA Cadarache, Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Aix Marseille Université (AMU), ITER organization (ITER), and icard, valerie
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[PHYS]Physics [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] ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2022
3. Gyrokinetic turbulence studies of the transition from open to closed field lines in tokamaks
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Donnel, Peter, Dif Pradalier, G., G. Di, Giannatale, Villard, L., V., Grandgirard, Nguyen, L., K., Obrejan, E., Bourne, X., Garbet, P., Ghendrih, Munschy, Yann, Y., Sarazin, R., Varennes, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Swiss Plasma Center (SPC), Ecole Polytechnique Fédérale de Lausanne (EPFL), DAM Île-de-France (DAM/DIF), Direction des Applications Militaires (DAM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA), and icard, valerie
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[PHYS]Physics [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] ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2022
4. Particle transport and heat loads in JT-60SA studied by SOLEDGE-EIRENE code
- Author
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Gałązka, K, Rivals, N, Tamain, P, Bufferand, H, Falchetto, G, Ciraolo, G, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), and icard, valerie
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[PHYS]Physics [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] ,[PHYS] Physics [physics] - Published
- 2022
5. UNDERSTANDING TUNGSTEN ACCUMULATION DURING ICRH OPERATION ON WEST
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Maget, P, Manas, P, Dumont, R, Angioni, C, Artaud, J-F, Bourdelle, C, Colas, L, Devynck, P, Fajardo, D, Fedorczak, N, Goniche, M, Hillairet, J, Huynh, Philippe, Morales, Jorge, Ostuni, Valeria, Vezinet, Didier, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Max-Planck-Institut für Plasmaphysik [Garching] (IPP), WEST team, Max-Planck-Institut, EPS, The WEST Team, European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), European Project: 101052200,Implementation of activities described in the Roadmap to Fusion during Horizon Europe through a joint programme of the members of the EUROfusion consortium,EUROfusion, WEST Team, 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, and EUROfusion - EUROfusion - - Implementation of activities described in the Roadmap to Fusion during Horizon Europe through a joint programme of the members of the EUROfusion consortium0000-00-00 - 0000-00-00 - 101052200 - VALID
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[PHYS]Physics [physics] ,[NLIN] Nonlinear Sciences [physics] ,[NLIN]Nonlinear Sciences [physics] - Abstract
International audience; y The transport of impurities in a tokamak with metallic walls can lead to accumulation events and radiative collapses, and this is particularly true when neoclassical transport is enhanced by sources of impurity poloidal asymmetry [1, 2]. On WEST, where the RF heating scheme (torque-free without core particle sources) is relevant for ITER operation, these events are rare, but still radiative collapses are sometimes observed [3, 4]. The physics of collisional tungsten transport in this case involves 3 main channels: i) a direct channel by which the hydrogen temperature anisotropy driven by ICRH drives a poloidal asymmetry of the electrostatic potential, ii) a non-linear channel by which the tungsten accumulation mitigates the ICRH drive by increasing the parallel temperature of the fast ions and reducing the temperature anisotropy in a self-limited process, and iii) an indirect channel related with the ICRH induced toroidal rotation. The role of Finite Orbit Width (FOW) effects is found to be instrumental : it strongly reduces the hydrogen temperature anisotropy, the favorable Hydrogen Temperature Screening (HTS) effect, and the electron heat source. The tungsten peaking as a function of toroidal rotation and ICRH power shows 2 possible branches consistent with bolometry inversion, one with a peaking driven by ICRH and one with a peaking driven by rotation. The condition for a radiative collapse in the core brings an additional constraint, and indicates that the electron heat source is probably much lower than computed, suggesting important losses of fast ions in the ripple. The radiative collapse would then be due to a limited electron heat source and a tungsten peaking driven by the induced rotation. This peaking is initially moderate, and it is reinforced during the collapse as the temperature screening effect reverses
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- 2022
6. Investigation of the Extreme-UV background emission in WEST tokamak
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Boumendjel, M., Guirlet, R., Desgranges, C., Schwob, J., Mandelbaum, P., Popov, E., Peyrusse, O., Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Racah Institute of Physics, Aix Marseille Université (AMU), West team, European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), icard, valerie, and 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
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[NLIN] Nonlinear Sciences [physics] ,[NLIN]Nonlinear Sciences [physics] - Abstract
International audience; Background & Motivations Analysis of a low temperature spectrum (T e ~ 1 keV) Conclusion & Perspectives
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- 2022
7. SOL modelling of the JT-60SA tokamak initial operational scenario using SOLEDGE-EIRENE code
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Gał Ązka, K., Balbinot, L., Falchetto, G., Rivals, N., Tamain, P., Marandet, Y., Bufferand, H., Innocente, P., Ciraolo, G., Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), IPPLM Institute of Plasma Physics and Laser Microfusion, 23 Hery Str., 01-497 Warsaw, Poland, Ricerca Formazione Innovazione (Consorzio RFX), National Research Council of Italy | Consiglio Nazionale delle Ricerche (CNR), Aix Marseille Université (AMU), EUROfusion Consortium, European Project: 101052200,Implementation of activities described in the Roadmap to Fusion during Horizon Europe through a joint programme of the members of the EUROfusion consortium,EUROfusion, icard, valerie, EUROfusion - EUROfusion - - Implementation of activities described in the Roadmap to Fusion during Horizon Europe through a joint programme of the members of the EUROfusion consortium0000-00-00 - 0000-00-00 - 101052200 - VALID, Physique des interactions ioniques et moléculaires (PIIM), and Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS)
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SOLEDGE3X-EIRENE ,SOL ,[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] ,JT-60SA ,tokamak ,Scrape-off layer plasma - Abstract
International audience; The main aim of this work is to assess the realistic heat loads on the first wall of the JT-60SA tokamak. To achieve this scope, for the first time the entire chamber and thesubdivertor region is modeled by the fluid transport code SOLEDGE3X-EIRENE [1]. Whereas the full power scenario #2 modeling was reported elsewhere [2] here wefocus on scenario #2 initial phase with carbon divertor and limited heating power Paux, which is the main scanned parameter. Standard computational mesh with pumpssituated next to the strike points (STD) is compared with full chamber + subdivertor mesh (SUBD)
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- 2022
8. Unraveling the competition/synergy between turbulence and 3D magnetic perturbations
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Varennes, Robin, Garbet, Xavier, Bourne, Emilie, Vermare, L., Sarazin, Yanick, Dif-Pradalier, Guilhem, Grandgirard, Virginie, Ghendrih, Philippe, Donnel, Peter, Peret, Mathieu, Obrejan, Kevin, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), 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), and icard, valerie
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[NLIN] Nonlinear Sciences [physics] ,[NLIN]Nonlinear Sciences [physics] - Abstract
International audience
- Published
- 2022
9. Improved understanding of energetic ions impact on plasma confinement from theory and experiments
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Garcia, J., Mazzi, Samuele, Kazakov, Ye, Ongena, J., Zarzoso, David, Dreval, M., Lin, W. H., Nocente, M., Stancar, Žiga, Szepesi, G., Eriksson, J., Ruiz, J., Sahlberg, Martin, Benkadda, Sadruddin, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Swiss Plasma Center (SPC), Ecole Polytechnique Fédérale de Lausanne (EPFL), Physique des interactions ioniques et moléculaires (PIIM), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), Laboratoire de physique des plasmas de l'ERM, Laboratorium voor plasmafysica van de KMS (LPP ERM KMS), Ecole Royale Militaire / Koninklijke Militaire School (ERM KMS), Kharkiv Institute of Physics and Technology (Ukraine), V.N. Karazin Kharkiv National University (KhNU), Southwestern Institute of Physics (SWIP), Università degli Studi di Milano-Bicocca = University of Milano-Bicocca (UNIMIB), Culham Science Centre [Abingdon], Department of Physics and Astronomy [Uppsala], Uppsala University, Rudolf Peierls Center for Theoretical Physics, University of Oxford, Aix Marseille Université (AMU), EPS, Jet contributors, EUROfusion Consortium, European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), European Project: 101052200,Implementation of activities described in the Roadmap to Fusion during Horizon Europe through a joint programme of the members of the EUROfusion consortium,EUROfusion, 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, and EUROfusion - EUROfusion - - Implementation of activities described in the Roadmap to Fusion during Horizon Europe through a joint programme of the members of the EUROfusion consortium0000-00-00 - 0000-00-00 - 101052200 - VALID
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[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] - Abstract
International audience
- Published
- 2022
10. Tungsten sources and core contamination in WEST plasmas: from experiments to simulations
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Fedorczak, N, Di Genova, S, Guillemaut, C, Guirlet, R, Cappelli, L, Gallo, A, Colas, L, Romazanov, J, Brezinsek, S, Marandet, Y, Bufferand, H, Yang, H, Ciraolo, G, Serre, E, Unterberg, E, Klepper, C, Johnson, C, Donovan, D, Kosslow, S, Maker, J, Grosjean, A, Tsitrone, E, Bucalossi, J, CEA Cadarache, Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Aix Marseille Université (AMU), Forschungszentrum Jülich GmbH, Physique des interactions ioniques et moléculaires (PIIM), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), CEA- Saclay (CEA), Laboratoire de Mécanique, Modélisation et Procédés Propres (M2P2), Aix Marseille Université (AMU)-École Centrale de Marseille (ECM)-Centre National de la Recherche Scientifique (CNRS), Oak Ridge National Laboratory [Oak Ridge] (ORNL), UT-Battelle, LLC, The University of Tennessee [Knoxville], and icard, valerie
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[PHYS]Physics [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] ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2022
11. First wall fluxes in ITER from full vessel edge-plasma simulations
- Author
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Rivals, Nicolas, Tamain, Patrick, Marandet, Y, Bonnin, X., Bufferand, Hugo, Falchetto, G., Yang, Hao, Ciraolo, Guido, Pitts, R.A., CEA Cadarache, Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Aix Marseille Université (AMU), ITER organization (ITER), and icard, valerie
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[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] - Abstract
International audience
- Published
- 2022
12. Non-linear MHD modelling of Edge Localized Modes suppression by Resonant Magnetic Perturbations in ITER
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M. Becoulet, G.T.A. Huijsmans, C. Passeron, Y.Q. Liu, T.E. Evans, L.L. Lao, L. Li, A. Loarte, S.D. Pinches, A. Polevoi, M. Hosokawa, S.K. Kim, S.J.P. Pamela, S. Futatani, null the JOREK Team, Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), General Atomics [San Diego], ITER organization (ITER), Princeton Plasma Physics Laboratory (PPPL), Princeton University, Culham Centre for Fusion Energy (CCFE), Universitat Politècnica de Catalunya [Barcelona] (UPC), the ITER IO Contract No. IO/19/CT/ 4300001845, European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), 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, EIRES Eng. for Sustainable Energy Systems, Magneto-Hydro-Dynamic Stability of Fusion Plasmas, Science and Technology of Nuclear Fusion, Eindhoven University of Technology [Eindhoven] (TU/e), and Donghua University [Shanghai]
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[PHYS]Physics [physics] ,Nuclear and High Energy Physics ,MHD ,ELMs ,code JOREK ,RMP ,JOREK ,Condensed Matter Physics ,Physics::Plasma Physics ,ITER ,10MA ,60kAt ITER SCENARIOS: 15MA 12.5MA ,ELM ,[NLIN] Nonlinear Sciences [physics] ,[NLIN]Nonlinear Sciences [physics] ,5.3T (initial conditions: ASTRA code [9]) - Abstract
Edge localized modes (ELMs) suppression by resonant magnetic perturbations (RMPs) was studied with the non-linear magneto-hydro-dynamic (MHD) code JOREK for the ITER H-mode scenarios at 15 MA, 12.5 MA, 10 MA/5.3 T. The main aim of this work was to demonstrate that ELMs can be suppressed by RMPs while the divertor 3D footprints of heat and particle fluxes remain within divertor material limits. The unstable peeling–ballooning modes responsible for ELMs without RMPs were modelled first for each scenario using numerically accessible parameters for ITER. Then the stabilization of ELMs by RMPs was modelled with the same parameters. RMP spectra, optimized by the linear MHD MARS-F code, with main toroidal harmonics N = 2, N = 3, N = 4 have been used as boundary conditions of the computational domain of JOREK, including realistic RMP coils, main plasma, scrape off layer (SOL) divertor and realistic first wall. The model includes all relevant plasma flows: toroidal rotation, two fluid diamagnetic effects and neoclassical poloidal friction. With RMPs, the main toroidal harmonic and the non-linearly coupled harmonics remain dominant at the plasma edge, producing saturated modes and a continuous MHD turbulent transport thereby avoiding ELM crashes in all scenarios considered here. The threshold for ELM suppression was found at a maximum RMP coils current of 45 kAt–60 kAt compared to the coils maximum capability of 90 kAt. In the high beta poloidal steady-state 10 MA/5.3 T scenario, a rotating QH-mode without ELMs was observed even without RMPs. In this scenario with RMPs N = 3, N = 4 at 20 kAt maximum current in RMP coils, similar QH-mode behaviour was observed however with dominant edge harmonic corresponding to the main toroidal number of RMPs. The present MHD modelling was limited in time by few tens of ms after RMPs were switched on until the magnetic energy of the modes saturates. As a consequence the thermal energy was still evolving on this time scale, far from the ITER confinement time scale and hence only the form of 3D footprints on the divertor targets can be indicated within this set-up. Also note, that the divertor physics was missing in this model, so realistic values of fluxes are out of reach in this modelling. However the stationary 3D divertor and particle fluxes could be simply extrapolated from these results to the stationary situation considering that a large power fraction should be radiated in the core and SOL and only about 50 MW power is going to the divertor, which is an arbitrary, but reasonable number used here. The 3D footprints with RMPs show the characteristic splitting with the main RMP toroidal symmetry. The maximum radial extension of the footprints typically was ∼20 cm in inner divertor and ∼40 cm in outer divertor with stationary heat fluxes decreasing further out from the initial strike point from ∼5 MW m−2 to ∼1 MW m−2 assuming a total power in the divertor and walls is 50 MW. The heat fluxes remain within the divertor target and baffle areas, however with rather small margin in the outer divertor which could be an issue for the first wall especially in transient regimes when part of the plasma thermal energy is released due to switching on the RMP coils. This fact should be considered when RMPs are applied with a more favorable application before or soon after the L–H transition, although optimization is required to avoid increasing the L–H power threshold with RMPs.
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- 2022
13. Deuterium-tritium experiments in JET with the ITER-like wall
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Garcia, Jeronimo, Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), JET contributors, European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), icard, valerie, and 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
- Subjects
[PHYS]Physics [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] ,ComputingMilieux_MISCELLANEOUS ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2022
14. Lower Hybrid Current Drive in High Aspect Ratio Tokamaks
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Marek Scholz, K. Król, J.-F. Artaud, A. Jardin, X. L. Zou, A. Ekedahl, Jakub Bielecki, J. Decker, Julien Hillairet, Y.P. Zhang, T. Hoang, D. Dworak, Didier Mazon, L. Delpech, Xingyu Bai, Y. Peysson, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Ecole Polytechnique Fédérale de Lausanne (EPFL), CEA, EUROFUSION, Natural Science Foundation of China (NSFC), HARMONIA Grant et PL-Grid Infrastructure, and icard, valerie
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Nuclear and High Energy Physics ,Tokamak ,Wave propagation ,52.50.sw ,Electron ,wave ,linear-theory ,01 natural sciences ,010305 fluids & plasmas ,law.invention ,[PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph] ,law ,0103 physical sciences ,Nuclear fusion ,010306 general physics ,Physics ,Toroid ,scattering ,diffusion ,52.55.wq ,Plasma ,Lower hybrid oscillation ,accessibility ,Computational physics ,operation ,Nuclear Energy and Engineering ,[PHYS.PHYS.PHYS-PLASM-PH] Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph] ,Spectral gap ,simulations - Abstract
International audience; A multi-machine study has been carried out to investigate the impact of a strongly bounded wave propagation domain on the Lower Hybrid current drive, a condition which occurs principally in high aspect ratio tokamaks. In this regime, the condition of kinetic resonance can be far above the upper boundary of the propagation domain, and may not be achieved by the usual toroidal upshift. Therefore no tail of fast electrons can be pulled out from the thermal bulk. Nevertheless, while tokamak plasmas are in principle almost transparent to the wave in this regime so-called "unbridgeable spectral gap", full current drive is well achieved for the two tokamaks considered in this study, TRIAM-1M [H. Zushi, et al., Nucl. Fusion 43 (2003) 1600] and WEST [C. Bourdelle, et al., Nucl. Fusion 55 (2015) 063017], both characterized by a very large aspect ratio R/a > 5.5. The case of the high aspect ratio tokamak HL-2A [Y. Liu et al. Nucl. Fusion 45 (2005) S239] for which the wave propagation domain has also an upper boundary, but close to the resonance condition, is considered by comparison. First principles modeling of the rf-driven current and the fast electron bremsstrahlung using the ALOHA/C3PO/LUKE/R5-X2 chain of codes shows unambiguously that the spectral gap must be already filled at the separatrix in order to reproduce quantitatively observations and some important parametric dependencies. This result is an important milestone in the physics understanding of the Lower Hybrid current drive, highlighting the existence of a powerful and likely universal alternative mechanism to bridge the spectral gap, that is not related to toroidal magnetic refraction. With an initially broad power spectrum, lobes with low parallel refractive indexes that carry most of the plasma current can be absorbed in almost single pass, restoring the full validity of the ray-tracing approximation for describing the propagation of the Lower Hybrid wave in cold plasmas.
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- 2020
15. Pellet core fueling in tokamaks, stellerators and reversed field pinches
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Geulin, Eleonore, Pégourié, Bernard, icard, valerie, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), and Commissariat à l'énergie atomique et aux énergies alternatives (CEA)
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[PHYS]Physics [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] ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2022
16. Characterization and integrated modelling of core radiative collapse in WEST plasmas
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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
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[PHYS]Physics [physics] ,ComputingMilieux_MISCELLANEOUS ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2022
17. Turbulent transport in magnetised plasmas
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Garbet, Xavier, icard, valerie, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), and Commissariat à l'énergie atomique et aux énergies alternatives (CEA)
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[NLIN] Nonlinear Sciences [physics] ,[NLIN]Nonlinear Sciences [physics] - Abstract
International audience
- Published
- 2022
18. A self-consistent cross-field transport model for edge tokamak plasma simulations: SOLEDGE modelling and comparison with experiments
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Ciraolo, G, Baschetti, S, Bufferand, H, Falchetto, G, Ghendrih, Ph, Yang, H, Rivals, N, Tamain, P, Serre, E, icard, valerie, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), and Aix Marseille Université (AMU)
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[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] - Abstract
International audience
- Published
- 2022
19. A model of interchange turbulent transport across separatrix with sheared flows
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Peret, Mathieu, Fedorczak, Nicolas, Vermare, Laure, Ramisch, M, Schmid, B, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), 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), Institut für Grenzflächenverfahrenstechnik und Plasmatechnologie (IGVP), Universität Stuttgart [Stuttgart], The WEST team, and icard, valerie
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[PHYS]Physics [physics] ,ComputingMilieux_MISCELLANEOUS ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2021
20. Impact of non-axisymmetric magnetic field perturbations on flows
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Varennes, R, Garbet, X, Vermare, L, Sarazin, Y, Grandgirard, V, Dif-Pradalier, Guilhem, Peret, M, Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), 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), European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), icard, valerie, and 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
- Subjects
[PHYS]Physics [physics] ,ComputingMilieux_MISCELLANEOUS ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2021
21. Extreme UV spectroscopy measurements and analysis for tungsten density studies in the WEST tokamak
- Author
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R Guirlet, C Desgranges, J L Schwob, P Mandelbaum, M Y Boumendjel, 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, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Racah Institute of Physics, Hebrew University of Jerusalem, Israel, Racah Institute of Physics (Racah Institute of Physics), The Hebrew University of Jerusalem (HUJ)-Racah Institute of Physics, The WEST Team, and European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014)
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[PHYS]Physics [physics] ,Nuclear Energy and Engineering ,Condensed Matter Physics ,[PHYS] Physics [physics] - Abstract
The VUV emission of tungsten in WEST is measured by an absolutely calibrated grazing incidence spectrometer of the Schwob–Fraenkel type, which can scan the lower half of the plasma. We have analysed the detected spectral lines in the range 120–140 Å and compared their behaviour with calculations and published information. We obtained an unambiguous identification of four intense and well-resolved spectral lines emitted by W42+-W45+ close to the magnetic axis in the analysed experiments. The measured spectral-line brightnesses are used to assess the Tungsten density in the emission region. In the case of a scanning line of sight, we investigate the possibility to calculate the Tungsten density profile from the angular brightness profiles. In a case of a fixed line of sight, we deduce from the measurements the core Tungsten density profile evolution during a radiative collapse.
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- 2022
22. HOW NITROGEN SEEDING SECURIZES PLASMA RAMP-UP IN THE METALLIC ENVIRONMENT OF WEST
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Maget, P, Artaud, J-F, Bourdelle, C, Bucalossi, J, Bufferand, H, Ciraolo, G, Desgranges, C, Devynck, P, Douai, D, Dumont, R, Fedorczak, N, Felici, F, Goniche, M, Guillemaut, C, Guirlet, R, Gunn, J, Ivanova-Stanik, I, Loarer, T, Manas, P, Morales, J, Moreau, P, Nouailletas, R, Reux, C, Sauter, O, Mulders, S, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Swiss Plasma Center (SPC), Ecole Polytechnique Fédérale de Lausanne (EPFL), EPS, WEST, European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), icard, valerie, and 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
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[PHYS]Physics [physics] ,ComputingMilieux_MISCELLANEOUS ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2021
23. Physical challenges & numerical issues in controlled fusion plasmas
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Sarazin, Yanick, Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Société de Mathématiques Appliquées et Industrielles (SMAI), Institut de Mathématiques de Toulouse, and icard, valerie
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[PHYS]Physics [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] ,ComputingMilieux_MISCELLANEOUS ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2021
24. Link between ablation and line emission for hydrogen fuelling pellet in LHD
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Geulin, E, Pégourié, B, Goto, M, Motojima, G, Sakamoto, R, Matsuyama, A, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), National Institute for Fusion Science (NIFS), National Institutes for Quantum and Radiological Science and Technology (QST), European physical society, EPS, and icard, valerie
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[PHYS]Physics [physics] ,Astrophysics::Galaxy Astrophysics ,[PHYS] Physics [physics] - Abstract
International audience; The unambiguous determination of ablation cloudlet characteristics requires the knowledge of calibrated images and spectrum. The model and procedure described here allows to evaluate:- The cloudlet geometry, density and temperature distributions,- The local (i.e. instantaneous) ablation rate,- The relation between line emission (H$\alpha$, H$\beta$ . . . ) and the ablation rate. No strict proportionality is observed between them.
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- 2021
25. Cross diagnostics measurements of heat load profiles on the lower tungsten divertor of WEST in L-mode experiments
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R. Mitteau, S. Brezinsek, R. Dejarnac, A. Grosjean, X. Courtois, J. P. Gunn, Yann Corre, T. Loarer, E. Tsitrone, Jérôme Bucalossi, Nicolas Fedorczak, Jonathan Gaspar, CEA, IRFM, F-13108, Saint Paul lez Durance, France, Institut universitaire des systèmes thermiques industriels (IUSTI), Centre National de la Recherche Scientifique (CNRS)-Aix Marseille Université (AMU), Institute of Plasma Physics, Association EURATOM (IPP PRAGUE), Czech Academy of Sciences [Prague] (CAS), Forschungszentrum Jülich GmbH | Centre de recherche de Juliers, Helmholtz-Gemeinschaft = Helmholtz Association, The West Team, European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), The National Fusion Research Institute (NFRI), Korea Nuclear Society, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), icard, valerie, and 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
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Nuclear and High Energy Physics ,Tokamak ,Materials science ,Materials Science (miscellaneous) ,01 natural sciences ,Temperature measurement ,[PHYS] Physics [physics] ,010305 fluids & plasmas ,law.invention ,Divertor ,law ,Diagnostics comparison ,[PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph] ,0103 physical sciences ,ComputingMilieux_MISCELLANEOUS ,010302 applied physics ,[PHYS]Physics [physics] ,Toroid ,Infra-red ,TK9001-9401 ,Plasma ,Magnetic flux ,Computational physics ,Nuclear Energy and Engineering ,Heat flux ,Thermocouples ,[PHYS.PHYS.PHYS-PLASM-PH] Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph] ,Thermography ,Nuclear engineering. Atomic power ,ddc:624 - Abstract
This is a PDF file of an article that has undergone enhancements after acceptance, such as the addition of a cover page and metadata, and formatting for readability, but it is not yet the definitive version of record. This version will undergo additional copyediting, typesetting and review before it is published in its final form, but we are providing this version to give early visibility of the article. Please note that, during the production process, errors may be discovered which could affect the content, and all legal disclaimers that apply to the journal pertain.; International audience; WEST is a full metallic tokamak with an extensive set of diagnostics for heat load measurements. In this paper, heat loads on the lower divertor of WEST are investigated using two independent methods. A first method relies on the thermal inversion of temperature measurements from arrays of thermal sensors embedded a few millimeters below the surface, while the second consists in the inversion of black body surface temperatures measured by infra-red (IR) thermography. The challenge of IR based temperature measurements in the full metal environment of WEST is addressed through a simplified model, allowing to correct for global reflections and low surface emissivities of tungsten surfaces. A large database ( L-mode discharges) is investigated. It is found that the energy absorbed by an outer divertor tile during a plasma discharge is closely estimated by the two diagnostics, over a large set of experimental conditions. A similar match is also found for the peak heat flux value on the outer target. The toroidal modulation of target heat loads by magnetic ripple is found to be consistent with the geometrical projection of a parallel heat flux component. Additionally, the heat flux channel width at the target is found to scale linearly with the magnetic flux expansion as expected. These observations give confidence in the robustness of the data from both diagnostics, and confirm the simple geometrical rules at use in the description of heat flux deposition on divertor targets. However, it is shown that the heat flux channel width estimated from infra-red thermography is about three times lower than the width estimated from embedded measurements, which is still under investigation.
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- 2021
26. Collisional transport and poloidal asymmetry distribution of impurities in tokamak plasmas, with application to WEST
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Maget, P., Manas, P., Dumont, R., J-F, Artaud, Bourdelle, C., Colas, L., Goniche, M., Garbet, X., Frank, J., Agullo, O., Nicolas, T., Hinrich Lütjens, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Physique des interactions ioniques et moléculaires (PIIM), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), Centre de Physique Théorique [Palaiseau] (CPHT), Centre National de la Recherche Scientifique (CNRS)-École polytechnique (X), HPC resources from GENCI (project 056348), The WEST team, European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), 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, and École polytechnique (X)-Centre National de la Recherche Scientifique (CNRS)
- Subjects
[PHYS.PHYS]Physics [physics]/Physics [physics] ,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] ,[PHYS.PHYS] Physics [physics]/Physics [physics] - Abstract
International audience; We report in this contribution on the development of an analytic model for a selfconsistent determination of the poloidal asymmetry, collisional flux and steady state profile of heavy impurities [1]. The model is compared with nonlinear axisymmetric simulations with the XTOR code [2, 3, 4], and with computations using the drift-kinetic code NEO [5]. An application to Tungsten peaking in the WEST tokamak under Ion Cyclotron Resonance Heating (ICRH) exemplifies the complex balance between accumulation and expulsion forces at play.
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- 2021
27. Collisional vertical f -asymmetry effect
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Maget, P, Frank, J, Manas, P, Dumont, R, Nicolas, T, Artaud, J-F, Bourdelle, C, Colas, L, Goniche, M, Agullo, O, Garbet, X, Lütjens, H, Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Physique des interactions ioniques et moléculaires (PIIM), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), Centre de Physique Théorique [Palaiseau] (CPHT), École polytechnique (X)-Centre National de la Recherche Scientifique (CNRS), HPC resources from GENCI (project 056348), IAEA, The WEST team, European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), Centre National de la Recherche Scientifique (CNRS)-École polytechnique (X), icard, valerie, and 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
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[PHYS]Physics [physics] ,[PHYS.PHYS]Physics [physics]/Physics [physics] ,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] ,[PHYS.PHYS] Physics [physics]/Physics [physics] ,[PHYS] Physics [physics] - Abstract
International audience; The use of metallic walls as plasma facing components in tokamaks puts severe constraints on the control of impurity contamination. Heavy impurities like Tungsten are of particular concern due to the high level of radiative losses they can induce. Moreover, their high sensitivity to neoclassical transport mechanisms exacerbated by toroidal rotation or electrostatic potential asymmetry generally explains experimental cases of strong accumulation in the plasma core. The poloidal distribution of the impurity modulates the amplitude of this neoclassical transport [Angioni14], with an asymmetry that often leads to enhancement, but that can also result in a reduction of the flux
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- 2021
28. Impact of the aspect ratio on tokamak reactor design
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Sarazin, Yanick, Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), and icard, valerie
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[PHYS]Physics [physics] ,ComputingMilieux_MISCELLANEOUS ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2021
29. Effect of partially ionized high-Z atoms on fast dynamics electron tokamak plasmas
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Peysson, Y., Mazon, D., Jardin, A., Kroll, K., Bielecki, J., Dworak, D., Scholz, M, Embreus, O., Hesslow, L., Fülop, T., Hoppe, M., Decker, J., Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), H. Niewodniczanski Institute of Nuclear Physics, Polska Akademia Nauk = Polish Academy of Sciences (PAN), Chalmers University of Technology [Göteborg], Ecole Polytechnique Fédérale de Lausanne (EPFL), and icard, valerie
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[PHYS.PHYS]Physics [physics]/Physics [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] ,[PHYS.PHYS] Physics [physics]/Physics [physics] ,ComputingMilieux_MISCELLANEOUS - Abstract
International audience
- Published
- 2021
30. Effect of partially ionized high-Z atoms on fast electron dynamics in tokamak plasmas
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Peysson, Y., Mazon, D., Jardin, A., Król, K, Bielecki, J, Dworak, D, Scholz, M, Embréus, O, Hesslow, L, Fülop, T, Hoppe, M, Decker, J, Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), H. Niewodniczanski Institute of Nuclear Physics, Polska Akademia Nauk = Polish Academy of Sciences (PAN), Chalmers University of Technology [Göteborg], Ecole Polytechnique Fédérale de Lausanne (EPFL), National Science Centre, Poland (NCN) grant HARMONIA, The WEST Team see also: http://west.cea.fr/WESTteam, European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), icard, valerie, and 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
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[PHYS]Physics [physics] ,[PHYS.PHYS]Physics [physics]/Physics [physics] ,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] ,[PHYS.PHYS] Physics [physics]/Physics [physics] ,[PHYS] Physics [physics] - Abstract
International audience; The dynamics of fast electrons driven inductively or by resonant interactions with radio-frequency waves is known to be highly sensitive to the presence of impurities in hot magnetized hydrogen plasmas. The possibility to use tungsten for the ITER divertor, thanks to its low tritium retention and high melting temperature, has raised the question of the impact of partially ionized high-Z atoms on current drive efficiency by enhancing pitch-angle scattering but also collisional slowing-down and inelastic scattering. Pioneering work on the impact of the screening effect of partially ionized atoms in kinetic calculations was carried out primarily for the problem of runaway electron mitigation in very cold post-disruptive plasmas [1]. In the present paper, this approach is adapted and extended to regular plasma regimes, allowing to take into account any type of high-Z metallic impurity in the plasma core on the fast electron dynamics and the non-thermal bremsstrahlung. This work has been implemented in LUKE Fokker-Planck solver [2] and the quantum relativistic radiation code R5-X2 [3] and the impact of partially ionized high-Z impurities on Lower Hybrid driven current in the WEST tokamak has been investigated.
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- 2021
31. Flux driven pedestal formation above a certain source Flux driven pedestal formation in tokamaks: Turbulence simulations validated against the isotope effect
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Bourdelle, C, de Dominici, G, Fuhr, G, Beyer, P, Chôné, L, Cianfrani, F, Falchetto, G, Garbet, X, Sarazin, Y, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Physique des interactions ioniques et moléculaires (PIIM), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), Aalto University, IAEA, and icard, valerie
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[PHYS]Physics [physics] ,ComputingMilieux_MISCELLANEOUS ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2021
32. Numerical study of the impact of fast ions on TEM-driven turbulence
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Mazzi, Samuele, Zarzoso, David, Garcia, Jeronimo, Benkadda, Sadruddin, Görler, Tobias, Siena, Alessandro, Camenen, yann, yoshida, Maiko, Hayashi, Nobuhiko, Shinohara, Kouji, Aix Marseille Université (AMU), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Max Planck Institute for Plasma physics (IPP-MPG), Max-Planck-Gesellschaft, National Institutes for Quantum and Radiological Science and Technology (QST), European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), icard, valerie, and 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
- Subjects
[PHYS]Physics [physics] ,[PHYS.PHYS]Physics [physics]/Physics [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] ,[PHYS.PHYS] Physics [physics]/Physics [physics] ,ComputingMilieux_MISCELLANEOUS ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2021
33. INTERPRETATIVE MODELING OF IMPURITY TRANSPORT AND TUNGSTEN SOURCES IN WEST BOUNDARY PLASMA
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Ciraolo, Guido, Di Genova, S., Gallo, Alberto, Fedorczak, Nicolas, Bucalossi, Jérôme, Bufferand, Hugo, Yang, Hao, Marandet, Yannick, Sepetys, Arvydas, Corre, Yann, Desgranges, Corinne, Guirlet, Remy, Guillemaut, Christophe, Gunn, J.P., Tamain, Patrick, Romazanov, J., Brezinsek, S, Klepper, C.C., Tsitrone, Emmanuelle, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Physique des interactions ioniques et moléculaires (PIIM), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), Forschungszentrum Jülich GmbH | Centre de recherche de Juliers, Helmholtz-Gemeinschaft = Helmholtz Association, Oak Ridge National Laboratory [Oak Ridge] (ORNL), UT-Battelle, LLC, WEST team - http://west.cea.fr/WESTteam, European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), icard, valerie, and 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
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[PHYS]Physics [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] ,ComputingMilieux_MISCELLANEOUS ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2021
34. Impact of fine divertor geometrical features on the modelling of JET corner configurations
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Fulvio Militello, H. Bufferand, G. Ciraolo, C. Giroud, N. Vianello, Patrick Tamain, Yannick Marandet, David Moulton, Jet Contributors, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), EURATOM/UKAEA, Culham Science Centre [Abingdon], Physique des interactions ioniques et moléculaires (PIIM), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), Ricerca Formazione Innovazione (Consorzio RFX), National Research Council of Italy | Consiglio Nazionale delle Ricerche (CNR), The National Fusion Research Institute (NFRI), Korea Nuclear Society, The JET contributors, European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), JET contributors, ANR-10-EQPX-0029,EQUIP@MESO,Equipement d'excellence de calcul intensif de Mesocentres coordonnés - Tremplin vers le calcul petaflopique et l'exascale(2010), Culham Centre for Fusion Energy (CCFE), CEA, IRFM, F-13108, Saint Paul lez Durance, France, Consiglio Nazionale delle Ricerche (CNR), icard, valerie, and 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
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Nuclear and High Energy Physics ,Field line ,Materials Science (miscellaneous) ,corner ,edge ,Flux ,Baffle ,Edge (geometry) ,01 natural sciences ,[PHYS] Physics [physics] ,010305 fluids & plasmas ,modelling ,Physics::Plasma Physics ,[PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph] ,0103 physical sciences ,Point (geometry) ,tokamak ,plasma ,ComputingMilieux_MISCELLANEOUS ,fluid ,010302 applied physics ,Physics ,[PHYS]Physics [physics] ,Jet (fluid) ,Divertor ,TK9001-9401 ,Mechanics ,Plasma ,Nuclear Energy and Engineering ,[PHYS.PHYS.PHYS-PLASM-PH] Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph] ,Nuclear engineering. Atomic power - Abstract
The modelling of JET corner configurations, in which the strike points are positioned deep in the corners of the divertor, is extremely challenging for edge plasma fluid modelling tools. To circumvent this technical limitation, a geometrical approximation has been proposed, consisting in considering an artificial minor modification of the geometry of the divertor targets plates. In this paper, we investigate how significantly this approximation impacts the output of transport simulations. Using the SOLEDGE2D-EIRENE transport code which has the unique capability to be able to cope with both the full and the approximated geometry, we have performed a density scan in H-mode for pulses in which the outer strike-point lies in the corner of the divertor. We report here how simulations in the artificial geometry differ from the ones in unaltered geometry. At the exception of low density cases, mid-plane profiles in the closed field lines region and the near scrape-off layer are little impacted. Further out however, in flux-surfaces that are concerned by the geometrical modification, we find that modifying the geometry leads to a strong overestimate of the plasma density. The density perturbation is not local and concerns the whole flux surfaces. Although the divertor geometry is modified only on the outer side, the largest impact is found at the inner divertor where densities are systematically overestimated by a factor that can exceed 10 in low density cases in the far Scrape-Off Layer (SOL) and temperature underestimated by 10 to 20 eV in most of the studied density range. The near SOL and strike point peak values are also impacted in the same direction with density changes by a factor of 2. As a consequence, the threshold to detachment of the inner divertor is found lower in the approximate geometry than in the unaltered one. Due to the large flux expansion between the outer and the inner target, the difference in plasma is especially sensitive at the top of the inner divertor baffle, which could have consequence on the evaluation of physical sputtering at that critical location.
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- 2021
35. Physics model development and extensive validation of predictive integrated modelling within the new EU framework programme 2021-2027 (TSVV11 activity)
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Bourdelle, Clarisse, Angioni, Clemente, Artaud, Jean-Francois, Camenen, Yann, Casson, Francis J., Citrin, Jonathan, Fable, E., Felici, F., Ho, A., Kochl, F., Maget, Patrick, Manas, Pierre, Morales, Jorge, Sauter, Olivier, Simpson, J., Tardini, G., Vandeplassche, K., 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, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Max Planck Institute for Plasma physics (IPP-MPG), Max-Planck-Gesellschaft, Centre National de la Recherche Scientifique (CNRS), Culham Centre for Fusion Energy (CCFE), Dutch Institute for Fundamental Energy Research [Eindhoven] (DIFFER), Ecole Polytechnique Fédérale de Lausanne (EPFL), EURATOM/CCFE Fusion Association, Culham Science Centre [Abingdon], and European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014)
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[PHYS]Physics [physics] ,[PHYS] Physics [physics] - Abstract
International audience; "a strong theory and modelling programme is essential because empirically based predictions are uncertain in unexplored environments like ITER and particularly DEMO, and this will be a stronger focus than foreseen earlier" [Statement from the 2018 Fusion Roadmap] In the EUROfusion Work Package Advanced Computing, among the 14 'Theory, Simulation, Verification and Validation ' activities one is devoted to such effort. The TSVV11 team plan to significantly extend the state-of-the-art in predictive integrated tokamak simulation, and validation methodologies thereof, combining both technical framework and physics-module advances. All the physics that we master in 2021 has to be available from ITER control room in 2027.
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- 2021
36. Impact of the aspect ratio on tokamak reactor design
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Sarazin, Y, Duchateau, J.-L, Garbet, X, Ghendrih, R, Guirlet, J, Hillairet, B, Pégourié, A, Torre, R, Varennes, R, and icard, valerie
- Subjects
[PHYS] Physics [physics] - Abstract
The impact of the aspect ratio R/a (major over minor radius) on the design of tokamak reactors is addressed by means of the generic and comprehensive 0-dimensional ScaLa model for tokamak dimensioning. The European DEMO (fusion gain Q=40 and power P$_{fus}$=2.037GW) is taken as the target. Three scaling laws are considered for the energy confinement time, namely IPB98(y,2) used as the ITER reference, the electrostatic DS03 law and the recently upgraded ITPA20 one. First, it appears that the increase of the energy confinement time with A found in two of the scaling laws does not necessarily result in an advantage of working at large A, cross-dependencies leading to sometimes counter-intuitiveyet realtrends. Second, the opposite trends with respect to a scan in A which is observed regarding the product of the plasma volume times the square of the magnetic fieldused as a proxy for the costdoes not provide a clear answer as to whether small or large aspect ratio tokamaks should be favoured. This mild conclusion pushes for consolidating experimental databases with tokamaks exhibiting aspect ratios departing from the common 3 value.
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- 2021
37. Thermal loads in gaps between ITER divertor monoblocks: first lessons learnt from WEST
- Author
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Marianne Richou, Marc Missirlian, C. Reux, E. Delmas, T. Loarer, M. Firdaouss, Eric Nardon, E. Tsitrone, Jonathan Gaspar, Jérôme Bucalossi, A. Grosjean, Nicolas Fedorczak, J. P. Gunn, M. Diez, P. Moreau, Yann Corre, icard, valerie, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut universitaire des systèmes thermiques industriels (IUSTI), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), The West Team, and The WEST team
- Subjects
010302 applied physics ,Nuclear and High Energy Physics ,Tokamak ,Toroid ,Materials science ,Steady state ,Materials Science (miscellaneous) ,Divertor ,Nuclear engineering ,TK9001-9401 ,Flux ,chemistry.chemical_element ,Deformation (meteorology) ,Tungsten ,01 natural sciences ,010305 fluids & plasmas ,law.invention ,Nuclear Energy and Engineering ,chemistry ,law ,[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] ,0103 physical sciences ,Thermal ,Nuclear engineering. Atomic power - Abstract
see also: http://west.cea.fr/WESTteam; International audience; In the WEST tokamak, ITER-like divertor targets consisting of tungsten monoblocks bonded via an OHFC-Cu compliance layer to CuCrZr cooling tubes were exposed to plasma during the 2018 experimental campaign in which modest heating power was available. Up to 2.5 MW/m$^2$ divertor surface heat flux was attained. Inspection of the components after the campaign revealed a wide variety of damage at both leading and trailing monoblock edges, and at the optical hot spots which are the projections along magnetic field lines of the toroidal gaps between monoblocks onto the poloidal leading edges. Cracking, deformation, and melting occurred. Consideration of the large body of past work on high heat flux testing, combined with the expected loading conditions in WEST, suggests that fractures form during the first transient events such as disruptions. Deformation occurs under subsequent exposure to steady state heat loads. Nearly identical damage was observed on reciprocating probes made of W-La(10%) alloy under measured irradiation conditions, lending credence to this hypothesis.
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- 2021
38. Key role of phase dynamics & diamagnetic drive on Reynolds stress in fusion plasma turbulence
- Author
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Sarazin, Y., Dif-Pradalier, Guilhem, Ghendrih, Ph., Garbet, X., Berger, A., Bigué, R., Bourne, Emilie, Grandgirard, Virginie, Obrejan, Kevin, Varennes, R., Vermare, L., 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, Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), 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), and European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014)
- Subjects
[PHYS]Physics [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] ,ComputingMilieux_MISCELLANEOUS ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2021
39. European Transport Simulator modeling of JET-ILW baseline plasmas: Predictive code validation and DTE2 predictions
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P. Huynh, E.A. Lerche, D. Van Eester, J. Garcia, T. Johnson, J. Ferreira, K.K. Kirov, D. Yadykin, P. Strand, null JET Contributors, null the EUROfusion-IM Team, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Laboratoire de physique des plasmas de l'ERM, Laboratorium voor plasmafysica van de KMS (LPP ERM KMS), Ecole Royale Militaire / Koninklijke Militaire School (ERM KMS), Culham Centre for Fusion Energy (CCFE), Royal Institute of Technology [Stockholm] (KTH ), Instituto Superior Técnico, Universidade Técnica de Lisboa (IST), Department of Space, Earth and Environment (SEE), Chalmers University of Technology [Göteborg], European Project, and icard, valerie
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Physics ,[PHYS]Physics [physics] ,Nuclear and High Energy Physics ,Jet (fluid) ,Tokamak ,plasma simulation ,Cyclotron ,DT extrapolation ,Plasma ,fusion power ,Fusion power ,Condensed Matter Physics ,Neutral beam injection ,law.invention ,Ion ,[PHYS] Physics [physics] ,Physics::Plasma Physics ,law ,JET ,integrated modelling ,ICRH and NBI synergy ,tokamak ,Simulation ,Beam (structure) ,ComputingMilieux_MISCELLANEOUS - Abstract
The European transport simulator is a fusion machine simulator useful for making predictions of high-performance fusion plasmas, in particular for DT reactors. Recent developments introducing self-consistent simulations of combined RF + NBI heating schemes in which majority, minority and beam ions are simultaneously heated is documented. The predictive simulations are first validated by comparison with the experimental data on a DD JET baseline plasma. In order to prepare the next JET DTE2 experimental campaign, extrapolations of fusion performance on DT plasma from DD plasma are made with a particular focus on ion cyclotron resonance heating (ICRH) computation. Traditional ion cyclotron range of frequency heating models do not permit the study of Coulomb collisional interaction of various ion species simultaneously including neutral beam injection ions, and generally forces one to consider only minority populations. Accounting for multi-population interaction is made possible here by solving coupled sets of Fokker-Planck equations for all ion species adopting the non-linear collision operator for arbitrary distribution functions, accounting for effects, such as the self-collisions of majority (or large minority) populations. To answer the question whether H minority scheme or He-3 minority ICRH scheme is better for boosting the DT fusion performance, minority concentration scans are produced.
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- 2021
40. The geometry of ICRF - Induced wave-SOL interaction
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Colas, L, Urbanczyk, G, Goniche, M, Hillairet, J, Bernard, J.-M, Bourdelle, C, Fedorczak, N, Guillemaut, C, Helou, W, Bobkov, V, Ochoukov, R, Jacquet, Ph, Zhang, X, Qin, C, Klepper, C, Lau, C, Wukitch, S, Lin, Y, Ono, M, icard, valerie, and 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
- Subjects
[PHYS.PHYS.PHYS-PLASM-PH] Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph] ,[PHYS] Physics [physics] - Abstract
As part of ITPA-IOS activities, this contribution reviews recent experimental characterization of Radio-Frequency(RF)-induced Scrape-Off Layer (SOL) modifications on various tokamaks worldwide and on the LArge Plasma Device(LAPD) at UCLA. The observed phenomenology, as observed using a large variety of measurement techniques, is consistentwith the expectations from RF-sheath rectification. Emphasis is then put on the complex 3-Dimensional (3D) spatial patternsof RF-SOL interaction, in relation to the magnetic topology and the spatial distribution of RF currents over the metallic structures surrounding the RF wave-launchers. Dependence on the local plasma parameters in the antenna vicinity is alsobriefly addressed. The final part discusses implications for future devices.
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- 2021
41. 2D imaging X-ray spectrometer on WEST : results and technical challenges
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VEZINET, Didier, DA ROS, Adrien, COLLEDANI, Gilles, Fenzi-Bonizec, C., BERTSCHINGER, G., icard, valerie, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), and Bertschinger GmbH & Co.
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[PHYS]Physics [physics] ,[PHYS] Physics [physics] - Abstract
International audience; A new imaging X-Ray spectrometer has been installed, aligned and used on the WEST tokamak. A typical experimental spectrum is presented for each of the 3 interchangeable crystals, measuring respectively the Ar XVII, Ar XVIII and Fe XXV spectra. The instrument function exhibits a distortion for the Ar XVII spectrum, presumably due to the crystal splitting in 2 stripes and non-parallelism of the crystal layers. The Ar XVII and Ar XVIII spectra also display blends of unidentified spectral lines, presumably W lines
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- 2021
42. Divertor power loads and scrape off layer width in the large aspect ratio full tungsten tokamak WEST
- Author
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J. Gaspar, Y. Corre, N. Fedorczak, J.P. Gunn, C. Bourdelle, S. Brezinsek, J. Bucalossi, N. Chanet, R. Dejarnac, M. Firdaouss, J.-L. Gardarein, G. Laffont, T. Loarer, C. Pocheau, E. Tsitrone, null the WEST Team, icard, valerie, INITIATIVE D'EXCELLENCE AIX MARSEILLE UNIVERSITE - - Amidex2011 - ANR-11-IDEX-0001 - IDEX - VALID, 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, Aix Marseille Université (AMU), Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institut fur Energie und Klimaforschung - Plasmaphysik (IEK-4), Forschungszentrum Jülich GmbH | Centre de recherche de Juliers, Helmholtz-Gemeinschaft = Helmholtz Association-Helmholtz-Gemeinschaft = Helmholtz Association, Institute of Plasma Physics [Praha], Czech Academy of Sciences [Prague] (CAS), Laboratoire Capteurs Fibres Optiques (LCFO), Département Métrologie Instrumentation & Information (DM2I), Laboratoire d'Intégration des Systèmes et des Technologies (LIST (CEA)), Direction de Recherche Technologique (CEA) (DRT (CEA)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Direction de Recherche Technologique (CEA) (DRT (CEA)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-Laboratoire d'Intégration des Systèmes et des Technologies (LIST (CEA)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay, The WEST team, ANR-11-IDEX-0001,Amidex,INITIATIVE D'EXCELLENCE AIX MARSEILLE UNIVERSITE(2011), European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), Institut universitaire des systèmes thermiques industriels (IUSTI), Aix Marseille Université (AMU)-Centre National de la Recherche Scientifique (CNRS), Laboratoire d'Intégration des Systèmes et des Technologies (LIST), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-Laboratoire d'Intégration des Systèmes et des Technologies (LIST), and Centre National de la Recherche Scientifique (CNRS)-Aix Marseille Université (AMU)
- Subjects
fusion ,Tokamak ,magnetic equilibrium ,WEST ,[SPI.OPTI] Engineering Sciences [physics]/Optics / Photonic ,diagnosis ,01 natural sciences ,7. Clean energy ,010305 fluids & plasmas ,law.invention ,law ,Thermocouple ,[PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph] ,sensor ,ITER ,Langmuir probe ,Fiber Bragg Grating ,nuclear instrumentation ,[SPI.MECA.THER] Engineering Sciences [physics]/Mechanics [physics.med-ph]/Thermics [physics.class-ph] ,instrumentation ,Divertor ,Condensed Matter Physics ,Magnetic flux ,thermocouple ,Heat flux ,[PHYS.PHYS.PHYS-PLASM-PH] Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph] ,infrared thermography ,symbols ,[SPI.MECA.THER]Engineering Sciences [physics]/Mechanics [physics.med-ph]/Thermics [physics.class-ph] ,heat measutrement ,ddc:620 ,Nuclear and High Energy Physics ,Materials science ,heat flux ,symbols.namesake ,0103 physical sciences ,heat load ,divertor ,[PHYS.PHYS.PHYS-INS-DET]Physics [physics]/Physics [physics]/Instrumentation and Detectors [physics.ins-det] ,010306 general physics ,tokamak ,plasma ,Steady state ,Plasma ,Computational physics ,Optical Fiber Sensor ,[PHYS.PHYS.PHYS-INS-DET] Physics [physics]/Physics [physics]/Instrumentation and Detectors [physics.ins-det] ,[SPI.OPTI]Engineering Sciences [physics]/Optics / Photonic ,thermal measurement - Abstract
International audience; WEST is a full W tokamak with an extensive set of diagnostics for heat load measurements especially in the lower divertor. It is composed by infrared (IR) thermography, thermal measurement with thermocouples (TC) and fiber Bragg grating (FBG) embedded few mm below the surface and flush mounted Langmuir probes (LP). A large database including different magnetic equilibrium and input power is investigated to compare the heat load pattern (location, amplitude of the peak and heat flux decay length) on the inner and outer strike point regions as function of the continuous progress achieved in WEST : from the first ohmic diverted plasma (obtained during the second experimental campaign C2 in 2018) up to the high power (up to 8 MW total injected) and high energy (up to 90 MJ injected energy in lower single null configuration) steady state experiments performed in the last experimental campaign (C4 in 2019). Concerning the peak location, a good agreement (
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- 2021
43. Formation of the radial electric field profile in WEST tokamak
- Author
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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.
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- 2021
44. Self-generated reversed radial electric field in 3D global flux-driven fluid edge plasma turbulence simulations
- Author
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Falchetto, Gloria, Tamain, Patrick, Bufferand, Hugo, Ciraolo, G., Fedorczak, Nicolas, Ghendrih, P, Laribi, Elias, Luce, Benjamin, Serre, Eric, Tatali, Raffaele, 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, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Laboratoire de Mécanique, Modélisation et Procédés Propres (M2P2), Aix Marseille Université (AMU)-École Centrale de Marseille (ECM)-Centre National de la Recherche Scientifique (CNRS), European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), and Centre National de la Recherche Scientifique (CNRS)-École Centrale de Marseille (ECM)-Aix Marseille Université (AMU)
- Subjects
[PHYS]Physics [physics] ,ComputingMilieux_MISCELLANEOUS ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2021
45. Interplay between core, edge and scrape-off layer in turbulent magnetised plasmas
- Author
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Dif-Pradalier, Guilhem, Ghendrih, Ph., Sarazin, Y., Garbet, X., Grandgirard, V, Munschy, Y., Varennes, R., Vermare, L., Camenen, Y., Widmer, F., 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, and Energy Oriented Center of Excellence : toward exascale for energy - EoCoE-II - - H2020-EU.1.4. - EXCELLENT SCIENCE - Research Infrastructures 2019-01-01 - 2022-06-30 - 824158 - VALID
- Subjects
[PHYS.PHYS.PHYS-PLASM-PH] Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph] ,[PHYS] Physics [physics] - Abstract
The present manuscript is meant to provide a companion pedagogical approach to an information theoretic measure, the "Transfer Entropy" method, useful to assess causality in complex (time series) datasets. This manuscript describes useful basics for the forthcoming discussion on the causal chain of events that leads to the onset of a spontaneous and stable edge transport barrier in flux-driven gyrokinetics when core, edge and scrape-off layer regions self-consistently interplay.
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- 2021
46. Simultaneous H/D/T and 3 He/ 4 He absolute concentration measurements
- Author
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Vartanian, S, Delabie, E, Klepper, C, Jepu, I, Jacquet, P, Lerche, E, Lomanowski, B, Colas, L, Dumont, R, Douai, D, Widdowson, A, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Oak Ridge National Laboratory [Oak Ridge] (ORNL), UT-Battelle, LLC, National Institute for Lasers, Plasma, and Radiation Physics [Magurele-Ilfov] (INFLPR), Culham Science Centre [Abingdon], Royal Military Academy (RMA), Eurofusion, oak ridge, CCFE, ERM-KMS, CEA, IRFMtraining programme 2014-2018 and 2019-2020 under grant agreement N° 633053, and icard, valerie
- Subjects
[PHYS]Physics [physics] ,ComputingMilieux_MISCELLANEOUS ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2020
47. ICRH coupling optimization and impurity behavior in EAST and WEST
- Author
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Urbanczyk, G., Colas, L., Zhang, X., Helou, W., Zhao, Y., Julien Hillairet, Gong, X., Lerche, E., Lombard, G., Ming, Q., Goniche, M., Ling, Z., Mollard, P., Bobkov, V., Yang, X., Meyer, O., Lu, L., Gunn, J., Yan, C., Desgranges, C., Bernard, J., Tiantian Zhang, Clairet, F., Pégourié, B., Dumont, R., Tierens, W., Eester, D., Durodié, F., Li, J., Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP), Laboratory for Plasma Physics (LPP), Ecole Royale Militaire / Koninklijke Militaire School (ERM KMS), Max-Planck-Institut für Plasmaphysik [Garching] (IPP), The EAST Team, The WEST Team - Culham Science Centre, Abingdon, UK, European Project: 633053,H2020,EURATOM-Adhoc-2014-20,EUROfusion(2014), icard, valerie, and 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
- Subjects
[PHYS]Physics [physics] ,[PHYS.PHYS]Physics [physics]/Physics [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] ,[PHYS.PHYS] Physics [physics]/Physics [physics] ,[PHYS] Physics [physics] - Abstract
International audience; This study compares experimental observations on the two challenges of Ion Cyclotron Resonance Heating (ICRH), namely the coupling of waves to the plasma and the enhanced plasma surface interactions in EAST and WEST medium size tokamaks. In WEST, Lower Hybrid (LH) power helps improving ICRH coupling. In both machines experiments reveal that fueling from the midplane not only helps to couple waves from nearby antennas like in other devices, but also has an impact on the scrape-off layer (SOL) density in regions that are not magnetically connected to the valves. Localized midplane nozzle valves allow similar (in WEST) or better (in EAST) coupling compared to poloidally distributed valves. Core density control requirements for long-pulse operation, in particular in L-mode regime, however limit the amount of gas that can be injected. During ICRH impurities can contaminate the plasma to a level detrimental for the operation, e.g. 100% of ICRH power radiated on WEST. In WEST, tungsten (W) production measured by visible spectroscopy increases on all the observed objects during ICRH compared to a reference phase without ICRH. On some components (antenna side limiters, baffle, divertor) the rise is larger than with a similar LH power. The relative contribution of each object and physical process (RF-sheaths, fast ion ripple losses) to core contamination yet remains poorly known. Comparing antenna limiters with W-coating vs low-Z materials would help quantifying the role of these components. In EAST, the core W content, measured by EUV spectroscopy in presence of divertor sources only, is correlated with the total injected power, either from ICRH or LH. Since 2018 the LH guard limiter tiles were W-coated. Their contribution to the core W content appears more important than divertor sources, when the magnetically connected ICRH antenna is powered. Two-strap ICRH antennas magnetically connected to W components at the midplane already compromise high performance operations.
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- 2020
48. Experimental and modeling development at JET for DT preparation and ITER risk mitigation
- Author
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Garcia, Jeronimo, Douai, D., Hillesheim, J., Huber, A., Maggi, C.F., Mailloux, J., Luna, E de la, Weisen, H., Sertoli, M., Mazzi, S., Frassinetti, L., King, D., Viezzer, E., Challis, C., Hobirk, J., Kappatou, A., Lerche, E., Kazakov, Y., Kiptily, V., Nocente, M., Ongena, J., Rimini, F., Garzotti, L., Eester, D. van, Frigione, D., Carvalho, P., Stancar, Z., Szepesi, G., Kim, H-T., Gallart, D., Zarzoso, D., Casson, F., Ho, A., Citrin, J., icard, valerie, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), and Commissariat à l'énergie atomique et aux énergies alternatives (CEA)
- Subjects
[PHYS]Physics [physics] ,ComputingMilieux_MISCELLANEOUS ,[PHYS] Physics [physics] - Abstract
International audience
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- 2020
49. Transport in Fusion Plasmas: Is the Tail Wagging the Dog?
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Guilhem Dif-Pradalier, Ph. Ghendrih, Sarazin, Y., Widmer, F., Camenen, Y., Garbet, X., Gillot, C., Grandgirard, V., laure vermare, icard, valerie, Institut de Recherche sur la Fusion par confinement Magnétique (IRFM), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Aix Marseille Université (AMU), Laboratoire de Physique des Plasmas (LPP), Observatoire de Paris, and 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)
- Subjects
[PHYS]Physics [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] ,ComputingMilieux_MISCELLANEOUS ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2020
50. Challenges in MHD modelling in fusion devices
- Author
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Huijsmans, Guido, icard, valerie, Association EURATOM-CEA (CEA/DSM/DRFC), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Eindhoven University of Technology [Eindhoven] (TU/e), and Institut de Recherche sur la Fusion par confinement Magnétique (IRFM)
- Subjects
[PHYS]Physics [physics] ,[NLIN] Nonlinear Sciences [physics] ,[NLIN]Nonlinear Sciences [physics] ,ComputingMilieux_MISCELLANEOUS ,[PHYS] Physics [physics] - Abstract
International audience
- Published
- 2020
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