Development of impurity seeding for divertor power flux handling in Wendelstein 7-X long pulse scenarios

International audience The handling and mitigation of high power fluxes onto the 3D-shaped main plasma facing components (PFCs) is an issue of critical importance during future long-pulse operations at Wendelstein 7-X (W7-X). Unmitigated heat fluxes would exceed critical material limits of currently...

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Main Authors: Effenberg, Florian, Barbui, T., Brezinsek, Sebastijan, Feng, Y., Frerichs, H., Geiger, J., Jakubowski, M., König, Ralf, Krychowiak, M., Lore, J.D., Naujoks, D, Niemann, H., Reimold, F., Schmitt, J.C., Schmitz, O., Pedersen, T. Sunn, Wurden, G.A., Zhang, D.
Other Authors: Princeton Plasma Physics Laboratory (PPPL), Princeton University, Institute of Energy and Climate Research - Plasma Physics (IEK-4), Forschungszentrum Jülich GmbH, Helmholtz-Gemeinschaft = Helmholtz Association-Helmholtz-Gemeinschaft = Helmholtz Association, Max-Planck-Institut für Plasmaphysik Garching (IPP), University of Wisconsin-Madison, Max-Planck-Institut fur Plasmaphysik Teilinstitut Greifswald, Wendelsteinstr. 1, 17491 Greifswald, Germany, Oak Ridge National Laboratory Oak Ridge (ORNL), UT-Battelle, LLC, Auburn University (AU), Los Alamos National Laboratory (LANL)
Format: Conference Object
Language:English
Published: HAL CCSD 2019
Subjects:
Online Access:https://hal.science/hal-03750211
https://hal.science/hal-03750211/document
https://hal.science/hal-03750211/file/ICFRM-2019-Poster-Florian-Effenberg.pdf
id ftccsdartic:oai:HAL:hal-03750211v1
record_format openpolar
institution Open Polar
collection Archive ouverte HAL (Hyper Article en Ligne, CCSD - Centre pour la Communication Scientifique Directe)
op_collection_id ftccsdartic
language English
topic stellarator
w7-x
divertor
island divertor
impurity seeding
detachment
emc3-eirene
nuclear fusion
nuclear reactor
plasma
divertor d'île
ensemencement d'impuretés
détachement
fusion nucléaire
réacteur nucléaire
[PHYS.PHYS]Physics [physics]/Physics [physics]
[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
[PHYS.HIST]Physics [physics]/Physics archives
[SPI.PLASMA]Engineering Sciences [physics]/Plasmas
[PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph]
[SPI]Engineering Sciences [physics]
[SPI.MAT]Engineering Sciences [physics]/Materials
spellingShingle stellarator
w7-x
divertor
island divertor
impurity seeding
detachment
emc3-eirene
nuclear fusion
nuclear reactor
plasma
divertor d'île
ensemencement d'impuretés
détachement
fusion nucléaire
réacteur nucléaire
[PHYS.PHYS]Physics [physics]/Physics [physics]
[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
[PHYS.HIST]Physics [physics]/Physics archives
[SPI.PLASMA]Engineering Sciences [physics]/Plasmas
[PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph]
[SPI]Engineering Sciences [physics]
[SPI.MAT]Engineering Sciences [physics]/Materials
Effenberg, Florian
Barbui, T.
Brezinsek, Sebastijan
Feng, Y.
Frerichs, H.
Geiger, J.
Jakubowski, M.
König, Ralf
Krychowiak, M.
Lore, J.D.
Naujoks, D
Niemann, H.
Reimold, F.
Schmitt, J.C.
Schmitz, O.
Pedersen, T. Sunn
Wurden, G.A.
Zhang, D.
Development of impurity seeding for divertor power flux handling in Wendelstein 7-X long pulse scenarios
topic_facet stellarator
w7-x
divertor
island divertor
impurity seeding
detachment
emc3-eirene
nuclear fusion
nuclear reactor
plasma
divertor d'île
ensemencement d'impuretés
détachement
fusion nucléaire
réacteur nucléaire
[PHYS.PHYS]Physics [physics]/Physics [physics]
[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
[PHYS.HIST]Physics [physics]/Physics archives
[SPI.PLASMA]Engineering Sciences [physics]/Plasmas
[PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph]
[SPI]Engineering Sciences [physics]
[SPI.MAT]Engineering Sciences [physics]/Materials
description International audience The handling and mitigation of high power fluxes onto the 3D-shaped main plasma facing components (PFCs) is an issue of critical importance during future long-pulse operations at Wendelstein 7-X (W7-X). Unmitigated heat fluxes would exceed critical material limits of currently 8 MWm-2 in attached phases and during plasma start-up. Higher plasma pressure and the evolution of the toroidal net-currents change the edge magnetic field geometry, shifting and focusing the strike lines on weaker parts of the divertor, risking overloading and melting in specific scenarios. This restricts the operational and configurational space for long-pulse operation. To address these issues and reduce the peak power fluxes and increase the widths of the wetted area, methods of power spreading and power dissipation are currently being developed. A promising technique is radiative power exhaust with seeded impurities. Experiments with neon (Ne) and nitrogen (N2) seeding in the standard island divertor configuration have demonstrated that the island divertor allows for stable plasma operation at enhanced radiative power losses reducing the power fluxes to the divertors by ~70% at the expense of a maximum loss in energy confinement of DtE≈15%. To prepare for long-pulse plasma scenarios seeding experiments have also been performed in configurations mimicking the evolution of the toroidal net-currents and plasma equilibrium effects by carefully adjusting the vacuum magnetic fields. The results show that the edge island geometry strongly determines the power and impurity exhaust and may be carefully adjusted to optimize for more stable and safe high radiative divertor operation. The effects of the magnetic field and impurities on the peak power fluxes and power widths will be discussed. 3D transport modeling with EMC3-EIRENE is used to analyze these effects and resolve the underlying main transport features. In particular, impurity seeding will be discussed with respect to its aim and suitability of detachment ...
author2 Princeton Plasma Physics Laboratory (PPPL)
Princeton University
Institute of Energy and Climate Research - Plasma Physics (IEK-4)
Forschungszentrum Jülich GmbH
Helmholtz-Gemeinschaft = Helmholtz Association-Helmholtz-Gemeinschaft = Helmholtz Association
Max-Planck-Institut für Plasmaphysik Garching (IPP)
University of Wisconsin-Madison
Max-Planck-Institut fur Plasmaphysik Teilinstitut Greifswald, Wendelsteinstr. 1, 17491 Greifswald, Germany
Oak Ridge National Laboratory Oak Ridge (ORNL)
UT-Battelle, LLC
Auburn University (AU)
Los Alamos National Laboratory (LANL)
format Conference Object
author Effenberg, Florian
Barbui, T.
Brezinsek, Sebastijan
Feng, Y.
Frerichs, H.
Geiger, J.
Jakubowski, M.
König, Ralf
Krychowiak, M.
Lore, J.D.
Naujoks, D
Niemann, H.
Reimold, F.
Schmitt, J.C.
Schmitz, O.
Pedersen, T. Sunn
Wurden, G.A.
Zhang, D.
author_facet Effenberg, Florian
Barbui, T.
Brezinsek, Sebastijan
Feng, Y.
Frerichs, H.
Geiger, J.
Jakubowski, M.
König, Ralf
Krychowiak, M.
Lore, J.D.
Naujoks, D
Niemann, H.
Reimold, F.
Schmitt, J.C.
Schmitz, O.
Pedersen, T. Sunn
Wurden, G.A.
Zhang, D.
author_sort Effenberg, Florian
title Development of impurity seeding for divertor power flux handling in Wendelstein 7-X long pulse scenarios
title_short Development of impurity seeding for divertor power flux handling in Wendelstein 7-X long pulse scenarios
title_full Development of impurity seeding for divertor power flux handling in Wendelstein 7-X long pulse scenarios
title_fullStr Development of impurity seeding for divertor power flux handling in Wendelstein 7-X long pulse scenarios
title_full_unstemmed Development of impurity seeding for divertor power flux handling in Wendelstein 7-X long pulse scenarios
title_sort development of impurity seeding for divertor power flux handling in wendelstein 7-x long pulse scenarios
publisher HAL CCSD
publishDate 2019
url https://hal.science/hal-03750211
https://hal.science/hal-03750211/document
https://hal.science/hal-03750211/file/ICFRM-2019-Poster-Florian-Effenberg.pdf
op_coverage La Jolla, United States
genre Edge Island
genre_facet Edge Island
op_source The 19th International Conference on Fusion Reactor Materials (ICFRM-19)
https://hal.science/hal-03750211
The 19th International Conference on Fusion Reactor Materials (ICFRM-19), Oct 2019, La Jolla, United States
op_relation hal-03750211
https://hal.science/hal-03750211
https://hal.science/hal-03750211/document
https://hal.science/hal-03750211/file/ICFRM-2019-Poster-Florian-Effenberg.pdf
op_rights info:eu-repo/semantics/OpenAccess
_version_ 1790599703706992640
spelling ftccsdartic:oai:HAL:hal-03750211v1 2024-02-11T10:03:28+01:00 Development of impurity seeding for divertor power flux handling in Wendelstein 7-X long pulse scenarios Développement de l'ensemencement d'impuretés pour la gestion du flux de puissance du divertor dans les scénarios d'impulsions longues Wendelstein 7-X Effenberg, Florian Barbui, T. Brezinsek, Sebastijan Feng, Y. Frerichs, H. Geiger, J. Jakubowski, M. König, Ralf Krychowiak, M. Lore, J.D. Naujoks, D Niemann, H. Reimold, F. Schmitt, J.C. Schmitz, O. Pedersen, T. Sunn Wurden, G.A. Zhang, D. Princeton Plasma Physics Laboratory (PPPL) Princeton University Institute of Energy and Climate Research - Plasma Physics (IEK-4) Forschungszentrum Jülich GmbH Helmholtz-Gemeinschaft = Helmholtz Association-Helmholtz-Gemeinschaft = Helmholtz Association Max-Planck-Institut für Plasmaphysik Garching (IPP) University of Wisconsin-Madison Max-Planck-Institut fur Plasmaphysik Teilinstitut Greifswald, Wendelsteinstr. 1, 17491 Greifswald, Germany Oak Ridge National Laboratory Oak Ridge (ORNL) UT-Battelle, LLC Auburn University (AU) Los Alamos National Laboratory (LANL) La Jolla, United States 2019-10-27 https://hal.science/hal-03750211 https://hal.science/hal-03750211/document https://hal.science/hal-03750211/file/ICFRM-2019-Poster-Florian-Effenberg.pdf en eng HAL CCSD hal-03750211 https://hal.science/hal-03750211 https://hal.science/hal-03750211/document https://hal.science/hal-03750211/file/ICFRM-2019-Poster-Florian-Effenberg.pdf info:eu-repo/semantics/OpenAccess The 19th International Conference on Fusion Reactor Materials (ICFRM-19) https://hal.science/hal-03750211 The 19th International Conference on Fusion Reactor Materials (ICFRM-19), Oct 2019, La Jolla, United States stellarator w7-x divertor island divertor impurity seeding detachment emc3-eirene nuclear fusion nuclear reactor plasma divertor d'île ensemencement d'impuretés détachement fusion nucléaire réacteur nucléaire [PHYS.PHYS]Physics [physics]/Physics [physics] [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex] [PHYS.HIST]Physics [physics]/Physics archives [SPI.PLASMA]Engineering Sciences [physics]/Plasmas [PHYS.PHYS.PHYS-PLASM-PH]Physics [physics]/Physics [physics]/Plasma Physics [physics.plasm-ph] [SPI]Engineering Sciences [physics] [SPI.MAT]Engineering Sciences [physics]/Materials info:eu-repo/semantics/conferenceObject Conference poster 2019 ftccsdartic 2024-01-21T00:22:25Z International audience The handling and mitigation of high power fluxes onto the 3D-shaped main plasma facing components (PFCs) is an issue of critical importance during future long-pulse operations at Wendelstein 7-X (W7-X). Unmitigated heat fluxes would exceed critical material limits of currently 8 MWm-2 in attached phases and during plasma start-up. Higher plasma pressure and the evolution of the toroidal net-currents change the edge magnetic field geometry, shifting and focusing the strike lines on weaker parts of the divertor, risking overloading and melting in specific scenarios. This restricts the operational and configurational space for long-pulse operation. To address these issues and reduce the peak power fluxes and increase the widths of the wetted area, methods of power spreading and power dissipation are currently being developed. A promising technique is radiative power exhaust with seeded impurities. Experiments with neon (Ne) and nitrogen (N2) seeding in the standard island divertor configuration have demonstrated that the island divertor allows for stable plasma operation at enhanced radiative power losses reducing the power fluxes to the divertors by ~70% at the expense of a maximum loss in energy confinement of DtE≈15%. To prepare for long-pulse plasma scenarios seeding experiments have also been performed in configurations mimicking the evolution of the toroidal net-currents and plasma equilibrium effects by carefully adjusting the vacuum magnetic fields. The results show that the edge island geometry strongly determines the power and impurity exhaust and may be carefully adjusted to optimize for more stable and safe high radiative divertor operation. The effects of the magnetic field and impurities on the peak power fluxes and power widths will be discussed. 3D transport modeling with EMC3-EIRENE is used to analyze these effects and resolve the underlying main transport features. In particular, impurity seeding will be discussed with respect to its aim and suitability of detachment ... Conference Object Edge Island Archive ouverte HAL (Hyper Article en Ligne, CCSD - Centre pour la Communication Scientifique Directe)