Experimental research on the TCV tokamak

Tokamak à configuration variable (TCV), recently celebrating 30 years of near-continual operation, continues in its missions to advance outstanding key physics and operational scenario issues for ITER and the design of future power plants such as DEMO. The main machine heating systems and operationa...

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Autores: Duval, B. P., Abdolmaleki, A., Agostini, M., Ajay, C. J., Alberti, S., Alessi, E., Anastasiou, G., Andrèbe, Y., Apruzzese, G. M., Ayllón Guerola, Juan Manuel, Galdón Quiroga, Joaquín, García Muñoz, Manuel, Gil, L., Zurita, M.
Tipo de recurso: artículo
Estado:Versión publicada
Fecha de publicación:2024
País:España
Institución:Universidad de Sevilla (US)
Repositorio:idUS. Depósito de Investigación de la Universidad de Sevilla
OAI Identifier:oai:idus.us.es:11441/165721
Acceso en línea:https://hdl.handle.net/11441/165721
https://doi.org/10.1088/1741-4326/ad8361
Access Level:acceso abierto
Palabra clave:EPFL
Plasma
Review
SPC
TCV
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repository_id_str
dc.title.none.fl_str_mv Experimental research on the TCV tokamak
title Experimental research on the TCV tokamak
spellingShingle Experimental research on the TCV tokamak
Duval, B. P.
EPFL
Plasma
Review
SPC
TCV
title_short Experimental research on the TCV tokamak
title_full Experimental research on the TCV tokamak
title_fullStr Experimental research on the TCV tokamak
title_full_unstemmed Experimental research on the TCV tokamak
title_sort Experimental research on the TCV tokamak
dc.creator.none.fl_str_mv Duval, B. P.
Abdolmaleki, A.
Agostini, M.
Ajay, C. J.
Alberti, S.
Alessi, E.
Anastasiou, G.
Andrèbe, Y.
Apruzzese, G. M.
Ayllón Guerola, Juan Manuel
Galdón Quiroga, Joaquín
García Muñoz, Manuel
Gil, L.
Zurita, M.
author Duval, B. P.
author_facet Duval, B. P.
Abdolmaleki, A.
Agostini, M.
Ajay, C. J.
Alberti, S.
Alessi, E.
Anastasiou, G.
Andrèbe, Y.
Apruzzese, G. M.
Ayllón Guerola, Juan Manuel
Galdón Quiroga, Joaquín
García Muñoz, Manuel
Gil, L.
Zurita, M.
author_role author
author2 Abdolmaleki, A.
Agostini, M.
Ajay, C. J.
Alberti, S.
Alessi, E.
Anastasiou, G.
Andrèbe, Y.
Apruzzese, G. M.
Ayllón Guerola, Juan Manuel
Galdón Quiroga, Joaquín
García Muñoz, Manuel
Gil, L.
Zurita, M.
author2_role author
author
author
author
author
author
author
author
author
author
author
author
author
dc.contributor.none.fl_str_mv Física Atómica, Molecular y Nuclear
Ingeniería Mecánica y Fabricación
EUROfusion Consortium
Department of Energy. United States
dc.subject.none.fl_str_mv EPFL
Plasma
Review
SPC
TCV
topic EPFL
Plasma
Review
SPC
TCV
description Tokamak à configuration variable (TCV), recently celebrating 30 years of near-continual operation, continues in its missions to advance outstanding key physics and operational scenario issues for ITER and the design of future power plants such as DEMO. The main machine heating systems and operational changes are first described. Then follow five sections: plasma scenarios. ITER Base-Line (IBL) discharges, triangularity studies together with X3 heating and N2 seeding. Edge localised mode suppression, with a high radiation region near the X-point is reported with N2 injection with and without divertor baffles in a snowflake configuration. Negative triangularity (NT) discharges attained record, albeit transient, βN ∼ 3 with lower turbulence, higher low-Z impurity transport, vertical stability and density limits and core transport better than the IBL. Positive triangularity L-Mode linear and saturated ohmic confinement confinement saturation, often-correlated with intrinsic toroidal rotation reversals, was probed for D, H and He working gases. H-mode confinement and pedestal studies were extended to low collisionality with electron cyclotron heating obtaining steady state electron iternal transport barrier with neutral beam heating (NBH), and NBH driven H-mode configurations with off-axis co-electron cyclotron current drive. Fast particle physics. The physics of disruptions, runaway electrons and fast ions (FIs) was developed using near-full current conversion at disruption with recombination thresholds characterised for impurity species (Ne, Ar, Kr). Different flushing gases (D2, H2) and pathways to trigger a benign disruption were explored. The 55 kV NBH II generated a rich Alfvénic spectrum modulating the FI fas ion loss detector signal. NT configurations showed less toroidal Alfvén excitation activity preferentially affecting higher FI pitch angles. Scrape-off layer and edge physics. gas puff imaging systems characterised turbulent plasma ejection for several advanced divertor configurations, including NT. Combined diagnostic array divertor state analysis in detachment conditions was compared to modelling revealing an importance for molecular processes. Divertor physics. Internal gas baffles diversified to include shorter/longer structures on the high and/or low field side to probe compressive efficiency. Divertor studies concentrated upon mitigating target power, facilitating detachment and increasing the radiated power fraction employing alternative divertor geometries, optimised X-point radiator regimes and long-legged configurations. Smaller-than-expected improvements with total flux expansion were better modelled when including parallel flows. Peak outer target heat flux reduction was achieved (>50%) for high flux-expansion geometries, maintaining core performance (H98 > 1). A reduction in target heat loads and facilitated detachment access at lower core densities is reported. Real-time control. TCV’s real-time control upgrades employed MIMO gas injector control of stable, robust, partial detachment and plasma β feedback control avoiding neoclassical tearing modes with plasma confinement changes. Machine-learning enhancements include trajectory tracking disruption proximity and avoidance as well as a first-of-its-kind reinforcement learning-based controller for the plasma equilibrium trained entirely on a free-boundary simulator. Finally, a short description of TCV’s immediate future plans will be given.
publishDate 2024
dc.date.none.fl_str_mv 2024
dc.type.none.fl_str_mv info:eu-repo/semantics/article
info:eu-repo/semantics/publishedVersion
format article
status_str publishedVersion
dc.identifier.none.fl_str_mv https://hdl.handle.net/11441/165721
https://doi.org/10.1088/1741-4326/ad8361
url https://hdl.handle.net/11441/165721
https://doi.org/10.1088/1741-4326/ad8361
dc.language.none.fl_str_mv Inglés
language_invalid_str_mv Inglés
dc.relation.none.fl_str_mv Nuclear Fusion, 64 (11), 112023.
101052200
DESC0010529
https://doi.org/10.1088/1741-4326/ad8361
dc.rights.none.fl_str_mv info:eu-repo/semantics/openAccess
eu_rights_str_mv openAccess
dc.format.none.fl_str_mv application/pdf
application/pdf
dc.publisher.none.fl_str_mv Institute of Physics Publishing
publisher.none.fl_str_mv Institute of Physics Publishing
dc.source.none.fl_str_mv reponame:idUS. Depósito de Investigación de la Universidad de Sevilla
instname:Universidad de Sevilla (US)
instname_str Universidad de Sevilla (US)
reponame_str idUS. Depósito de Investigación de la Universidad de Sevilla
collection idUS. Depósito de Investigación de la Universidad de Sevilla
repository.name.fl_str_mv
repository.mail.fl_str_mv
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spelling Experimental research on the TCV tokamakDuval, B. P.Abdolmaleki, A.Agostini, M.Ajay, C. J.Alberti, S.Alessi, E.Anastasiou, G.Andrèbe, Y.Apruzzese, G. M.Ayllón Guerola, Juan ManuelGaldón Quiroga, JoaquínGarcía Muñoz, ManuelGil, L.Zurita, M.EPFLPlasmaReviewSPCTCVTokamak à configuration variable (TCV), recently celebrating 30 years of near-continual operation, continues in its missions to advance outstanding key physics and operational scenario issues for ITER and the design of future power plants such as DEMO. The main machine heating systems and operational changes are first described. Then follow five sections: plasma scenarios. ITER Base-Line (IBL) discharges, triangularity studies together with X3 heating and N2 seeding. Edge localised mode suppression, with a high radiation region near the X-point is reported with N2 injection with and without divertor baffles in a snowflake configuration. Negative triangularity (NT) discharges attained record, albeit transient, βN ∼ 3 with lower turbulence, higher low-Z impurity transport, vertical stability and density limits and core transport better than the IBL. Positive triangularity L-Mode linear and saturated ohmic confinement confinement saturation, often-correlated with intrinsic toroidal rotation reversals, was probed for D, H and He working gases. H-mode confinement and pedestal studies were extended to low collisionality with electron cyclotron heating obtaining steady state electron iternal transport barrier with neutral beam heating (NBH), and NBH driven H-mode configurations with off-axis co-electron cyclotron current drive. Fast particle physics. The physics of disruptions, runaway electrons and fast ions (FIs) was developed using near-full current conversion at disruption with recombination thresholds characterised for impurity species (Ne, Ar, Kr). Different flushing gases (D2, H2) and pathways to trigger a benign disruption were explored. The 55 kV NBH II generated a rich Alfvénic spectrum modulating the FI fas ion loss detector signal. NT configurations showed less toroidal Alfvén excitation activity preferentially affecting higher FI pitch angles. Scrape-off layer and edge physics. gas puff imaging systems characterised turbulent plasma ejection for several advanced divertor configurations, including NT. Combined diagnostic array divertor state analysis in detachment conditions was compared to modelling revealing an importance for molecular processes. Divertor physics. Internal gas baffles diversified to include shorter/longer structures on the high and/or low field side to probe compressive efficiency. Divertor studies concentrated upon mitigating target power, facilitating detachment and increasing the radiated power fraction employing alternative divertor geometries, optimised X-point radiator regimes and long-legged configurations. Smaller-than-expected improvements with total flux expansion were better modelled when including parallel flows. Peak outer target heat flux reduction was achieved (>50%) for high flux-expansion geometries, maintaining core performance (H98 > 1). A reduction in target heat loads and facilitated detachment access at lower core densities is reported. Real-time control. TCV’s real-time control upgrades employed MIMO gas injector control of stable, robust, partial detachment and plasma β feedback control avoiding neoclassical tearing modes with plasma confinement changes. Machine-learning enhancements include trajectory tracking disruption proximity and avoidance as well as a first-of-its-kind reinforcement learning-based controller for the plasma equilibrium trained entirely on a free-boundary simulator. Finally, a short description of TCV’s immediate future plans will be given.EUROfusion Consortium 101052200US Department of Energy DESC0010529Institute of Physics PublishingFísica Atómica, Molecular y NuclearIngeniería Mecánica y FabricaciónEUROfusion ConsortiumDepartment of Energy. United States2024info:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersionapplication/pdfapplication/pdfhttps://hdl.handle.net/11441/165721https://doi.org/10.1088/1741-4326/ad8361reponame:idUS. Depósito de Investigación de la Universidad de Sevillainstname:Universidad de Sevilla (US)InglésNuclear Fusion, 64 (11), 112023.101052200DESC0010529https://doi.org/10.1088/1741-4326/ad8361info:eu-repo/semantics/openAccessoai:idus.us.es:11441/1657212026-06-17T12:51:07Z
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