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...
Main Authors: | , , , , , , , , , , , , , , , , , |
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Format: | Conference Object |
Language: | English |
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HAL CCSD
2019
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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 |
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ftccsdartic:oai:HAL:hal-03750211v1 |
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Open Polar |
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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) |