Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development

An overview of recent results obtained at the tokamak ASDEX Upgrade (AUG) is given. A work flow for predictive profile modelling of AUG discharges was established which is able to reproduce experimental H-mode plasma profiles based on engineering parameters only. In the plasma center, theoretical pr...

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Autores: Stroth, U., Aguiam, D., Alessi, E., Angioni, C., Arden, N., Parra, R. Arredondo, Cano Megías, Pilar, Cruz Zabala, Diego José, Domínguez-Palacios Durán, Jesús José, García Muñoz, Manuel, González Martín, Javier, Rivero Rodríguez, Juan Francisco, Rodríguez Ramos, Mauricio, Sanchís Sánchez, Lucía, Van Vuuren, Anton Jansen, Viezzer, Eleonora, EUROfusion MST1 Team
Tipo de recurso: artículo
Estado:Versión publicada
Fecha de publicación:2022
País:España
Institución:Universidad de Sevilla (US)
Repositorio:idUS. Depósito de Investigación de la Universidad de Sevilla
OAI Identifier:oai:idus.us.es:11441/161530
Acceso en línea:https://hdl.handle.net/11441/161530
https://doi.org/10.1088/1741-4326/ac207f
Access Level:acceso abierto
Palabra clave:Asdex Upgrade
Confinement
ELLM-free discharges
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spelling Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario developmentStroth, U.Aguiam, D.Alessi, E.Angioni, C.Arden, N.Parra, R. ArredondoCano Megías, PilarCruz Zabala, Diego JoséDomínguez-Palacios Durán, Jesús JoséGarcía Muñoz, ManuelGonzález Martín, JavierRivero Rodríguez, Juan FranciscoRodríguez Ramos, MauricioSanchís Sánchez, LucíaVan Vuuren, Anton JansenViezzer, EleonoraEUROfusion MST1 TeamAsdex UpgradeConfinementELLM-free dischargesAn overview of recent results obtained at the tokamak ASDEX Upgrade (AUG) is given. A work flow for predictive profile modelling of AUG discharges was established which is able to reproduce experimental H-mode plasma profiles based on engineering parameters only. In the plasma center, theoretical predictions on plasma current redistribution by a dynamo effect were confirmed experimentally. For core transport, the stabilizing effect of fast ion distributions on turbulent transport is shown to be important to explain the core isotope effect and improves the description of hollow low-Z impurity profiles. The L-H power threshold of hydrogen plasmas is not affected by small helium admixtures and it increases continuously from the deuterium to the hydrogen level when the hydrogen concentration is raised from 0 to 100%. One focus of recent campaigns was the search for a fusion relevant integrated plasma scenario without large edge localised modes (ELMs). Results from six different ELM-free confinement regimes are compared with respect to reactor relevance: ELM suppression by magnetic perturbation coils could be attributed to toroidally asymmetric turbulent fluctuations in the vicinity of the separatrix. Stable improved confinement mode plasma phases with a detached inner divertor were obtained using a feedback control of the plasma β. The enhanced D α H-mode regime was extended to higher heating power by feedback controlled radiative cooling with argon. The quasi-coherent exhaust regime was developed into an integrated scenario at high heating power and energy confinement, with a detached divertor and without large ELMs. Small ELMs close to the separatrix lead to peeling-ballooning stability and quasi continuous power exhaust. Helium beam density fluctuation measurements confirm that transport close to the separatrix is important to achieve the different ELM-free regimes. Based on separatrix plasma parameters and interchange-drift-Alfvén turbulence, an analytic model was derived that reproduces the experimentally found important operational boundaries of the density limit and between L- and H-mode confinement. Feedback control for the X-point radiator (XPR) position was established as an important element for divertor detachment control. Stable and detached ELM-free phases with H-mode confinement quality were obtained when the XPR was moved 10 cm above the X-point. Investigations of the plasma in the future flexible snow-flake divertor of AUG by means of first SOLPS-ITER simulations with drifts activated predict beneficial detachment properties and the activation of an additional strike point by the drifts.EUROfusion Consortium 633053Institute of Physics PublishingFísica Atómica, Molecular y NuclearEUROfusion Consortium2022info:eu-repo/semantics/articleinfo:eu-repo/semantics/publishedVersionapplication/pdfapplication/pdfhttps://hdl.handle.net/11441/161530https://doi.org/10.1088/1741-4326/ac207freponame:idUS. Depósito de Investigación de la Universidad de Sevillainstname:Universidad de Sevilla (US)InglésNuclear Fusion, 62 (4), 042006.633053https://doi.org/10.1088/1741-4326/ac207finfo:eu-repo/semantics/openAccessoai:idus.us.es:11441/1615302026-06-17T12:51:07Z
dc.title.none.fl_str_mv Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development
title Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development
spellingShingle Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development
Stroth, U.
Asdex Upgrade
Confinement
ELLM-free discharges
title_short Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development
title_full Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development
title_fullStr Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development
title_full_unstemmed Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development
title_sort Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development
dc.creator.none.fl_str_mv Stroth, U.
Aguiam, D.
Alessi, E.
Angioni, C.
Arden, N.
Parra, R. Arredondo
Cano Megías, Pilar
Cruz Zabala, Diego José
Domínguez-Palacios Durán, Jesús José
García Muñoz, Manuel
González Martín, Javier
Rivero Rodríguez, Juan Francisco
Rodríguez Ramos, Mauricio
Sanchís Sánchez, Lucía
Van Vuuren, Anton Jansen
Viezzer, Eleonora
EUROfusion MST1 Team
author Stroth, U.
author_facet Stroth, U.
Aguiam, D.
Alessi, E.
Angioni, C.
Arden, N.
Parra, R. Arredondo
Cano Megías, Pilar
Cruz Zabala, Diego José
Domínguez-Palacios Durán, Jesús José
García Muñoz, Manuel
González Martín, Javier
Rivero Rodríguez, Juan Francisco
Rodríguez Ramos, Mauricio
Sanchís Sánchez, Lucía
Van Vuuren, Anton Jansen
Viezzer, Eleonora
EUROfusion MST1 Team
author_role author
author2 Aguiam, D.
Alessi, E.
Angioni, C.
Arden, N.
Parra, R. Arredondo
Cano Megías, Pilar
Cruz Zabala, Diego José
Domínguez-Palacios Durán, Jesús José
García Muñoz, Manuel
González Martín, Javier
Rivero Rodríguez, Juan Francisco
Rodríguez Ramos, Mauricio
Sanchís Sánchez, Lucía
Van Vuuren, Anton Jansen
Viezzer, Eleonora
EUROfusion MST1 Team
author2_role author
author
author
author
author
author
author
author
author
author
author
author
author
author
author
author
dc.contributor.none.fl_str_mv Física Atómica, Molecular y Nuclear
EUROfusion Consortium
dc.subject.none.fl_str_mv Asdex Upgrade
Confinement
ELLM-free discharges
topic Asdex Upgrade
Confinement
ELLM-free discharges
description An overview of recent results obtained at the tokamak ASDEX Upgrade (AUG) is given. A work flow for predictive profile modelling of AUG discharges was established which is able to reproduce experimental H-mode plasma profiles based on engineering parameters only. In the plasma center, theoretical predictions on plasma current redistribution by a dynamo effect were confirmed experimentally. For core transport, the stabilizing effect of fast ion distributions on turbulent transport is shown to be important to explain the core isotope effect and improves the description of hollow low-Z impurity profiles. The L-H power threshold of hydrogen plasmas is not affected by small helium admixtures and it increases continuously from the deuterium to the hydrogen level when the hydrogen concentration is raised from 0 to 100%. One focus of recent campaigns was the search for a fusion relevant integrated plasma scenario without large edge localised modes (ELMs). Results from six different ELM-free confinement regimes are compared with respect to reactor relevance: ELM suppression by magnetic perturbation coils could be attributed to toroidally asymmetric turbulent fluctuations in the vicinity of the separatrix. Stable improved confinement mode plasma phases with a detached inner divertor were obtained using a feedback control of the plasma β. The enhanced D α H-mode regime was extended to higher heating power by feedback controlled radiative cooling with argon. The quasi-coherent exhaust regime was developed into an integrated scenario at high heating power and energy confinement, with a detached divertor and without large ELMs. Small ELMs close to the separatrix lead to peeling-ballooning stability and quasi continuous power exhaust. Helium beam density fluctuation measurements confirm that transport close to the separatrix is important to achieve the different ELM-free regimes. Based on separatrix plasma parameters and interchange-drift-Alfvén turbulence, an analytic model was derived that reproduces the experimentally found important operational boundaries of the density limit and between L- and H-mode confinement. Feedback control for the X-point radiator (XPR) position was established as an important element for divertor detachment control. Stable and detached ELM-free phases with H-mode confinement quality were obtained when the XPR was moved 10 cm above the X-point. Investigations of the plasma in the future flexible snow-flake divertor of AUG by means of first SOLPS-ITER simulations with drifts activated predict beneficial detachment properties and the activation of an additional strike point by the drifts.
publishDate 2022
dc.date.none.fl_str_mv 2022
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/11441/161530
https://doi.org/10.1088/1741-4326/ac207f
url https://hdl.handle.net/11441/161530
https://doi.org/10.1088/1741-4326/ac207f
dc.language.none.fl_str_mv Inglés
language_invalid_str_mv Inglés
dc.relation.none.fl_str_mv Nuclear Fusion, 62 (4), 042006.
633053
https://doi.org/10.1088/1741-4326/ac207f
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
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