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Effect of diamagnetic flow stabilization on pedestal stability in JET and its importance for isotope mass effects
KTH, School of Electrical Engineering and Computer Science (EECS), Electrical Engineering, Electromagnetic Engineering and Fusion Science.ORCID iD: 0000-0002-1310-4517
Max Planck Institute for Plasma Physics, Garching, Germany.
Max Planck Institute for Plasma Physics, Garching, Germany.
KTH, School of Electrical Engineering and Computer Science (EECS), Electrical Engineering, Electromagnetic Engineering and Fusion Science.ORCID iD: 0000-0002-9546-4494
2025 (English)Conference paper, Poster (with or without abstract) (Other academic)
Abstract [en]

Changing the isotope mass from deuterium to tritium in JET-ILW leads to an increase in the electron pedestal pressure (peped) due to an increase in the electron pedestal density (neped) [1]. The increase of the pressure with increasing effective mass (Aeff) has been explained via resistive MHD and by a change in the diamagnetic stabilization [1]. The results discussed in [1] were however obtained with a simple model for the diamagnetic stabilization. The present work aims to more properly model these effects using the code JOREK [2], which self-consistently treats the diamagnetic flows. The analysis has started with the JET deuterium shot 96208 at 2MA/2.3T. The pedestal height has then been increased, by adding heat and particle sources at the pedestal top, until an unstable mode starts growing. When the Teped is increased at fixed neped, no unstable modes are found. However, when neped is increased at fixed Teped a ballooning mode is driven unstable by just a small increase in the density. This can be explained by the fact that the diamagnetic frequency, which scales as ω* ∝ ∇p/n, also increases with the pressure gradient drive when Teped is increased but when neped is increased there is a negligible change in the diamagnetic frequency. This shows that the balance between the diamagnetic stabilization and the instability drive is the key to understanding the ELM-triggering mechanism in this plasma (and not just the instability drive itself). This has also been noted in previous studies of type-I ELMy pedestals [3]. To assess the effect of the isotope mass, Aeff has been changed from 2 to 3. The increase in Aeff led to a higher critical neped. This increase in neped is comparable to the increase in neped that is achieved by only rescaling the diamagnetic flow terms consistent with a change from Aeff = 2 to 3. We can therefore conclude that it is the change in the diamagnetic flows that increases neped when we go from deuterium to tritium. Quantitatively, the predicted increase in neped is smaller than the one seen in experiment, but qualitatively a good agreement is obtained.

References[1] L. Frassinetti et al 2023 Nucl. Fusion 63 112009[2] M. Hoelzl et al 2021 Nucl. Fusion 61 065001[3] A. Cathey et al 2020 Nucl. Fusion 60 124007

Place, publisher, year, edition, pages
2025. , p. 4
National Category
Fusion, Plasma and Space Physics
Identifiers
URN: urn:nbn:se:kth:diva-372549OAI: oai:DiVA.org:kth-372549DiVA, id: diva2:2012708
Conference
51st EPS Conference on Plasma Physics, Vilnius, July 7-11, 2025
Note

QC 20251110

Available from: 2025-11-10 Created: 2025-11-10 Last updated: 2025-11-10Bibliographically approved
In thesis
1. Magnetohydrodynamic stability of non-ideally peeling-ballooning limited pedestals in JET
Open this publication in new window or tab >>Magnetohydrodynamic stability of non-ideally peeling-ballooning limited pedestals in JET
2025 (English)Doctoral thesis, comprehensive summary (Other academic)
Abstract [en]

Fusion power is a promising candidate for providing large amounts of sustainable, planable power to complement other sustainable energy solutions in the future. The tokamak, which is the fusion device furthest along to achieving this goal, confines a hot plasma with the help of magnetic fields. The performance of the tokamak is highly dependent on the performance of a thin region near the plasma edge, called the pedestal. Accurate models for predicting the pedestal behavior is therefore paramount for the optimization of future fusion reactors. The pedestal height is typically limited by the onset of ideal magnetohydrodynamic (MHD) instabilities called edge localized modes (ELMs). In the JET tokamak, it has however been observed that sometimes the pre-ELM pedestal can sometimes be stable to ideal MHD modes.

This thesis investigates the physics which are required to reconcile modeling and experimental results in pedestals which are not marginally unstable to ideal MHD modes when the ELM is triggered. It is shown that a key component that seems to be missing is the lack of resistivity in the MHD modeling. To investigate the impact of resistivity on the MHD modeling, a resistive MHD code has been implemented into the MHD stability frameworks used at JET. Including the resistivity improves the agreement between model and experiment compared to ideal MHD. In particular, the impact of changing the main fuel isotope mass and the impurity content on the pedestal performance is captured when resistive MHD is used.

Abstract [sv]

Fusion är en lovande källa av stora mängder hållbar och planerbar energi som kan kompletera andra hållbara energilösningar i framtiden. Tokamaken, som är det fusionskoncept som har kommit längst på vägen för att uppnå detta mål, innesluter ett varmt plasma med hjälp av magnetiska fält. Tokamakens prestanda är hårt bunden till prestandan hos en liten region nära kanten på plasmat som kallas pedestalen. För att kunna optimera framtida fusionsreaktorer så krävs pålitliga modeller för att förutspå pedestalens beteende. Höjden på pedestalen är oftast begränsad av ideala magnetohydrodynamiska (MHD) instabiliteter som kallas edge localized modes (ELMs). I tokamaken JET, så har det dock obeserverats att pedestalen ibland är stabil mot ideala MHD instabiliteter precis innan en ELM.

Den här avhandlingen undersöker vilken ytterligare fysik som krävs för att försona de teoretiska modellerna med de experimentella resultaten, när pedestalen inte är marginellt instabil mot ideala MHD moder när en ELM utlöses. Det visas att en nyckelkomponent är bristen på resistivitet i MHD modelleringen. För att undersöka effekten av att inkludera resistivitet på MHD modeleringen, så har en resistiv MHD kod blivit implementerad i MHD stabilitetsramverken som används på JET. Inkluderandet av resistivitet leder till att resultaten från simuleringarna stämmer bättre överens med de experimentella resultaten. Inkluderandet av resistivitet i modeleringen låter en även fånga effekten på pedestalen från en ändring av bränsleisotop och föroreningar i plasmat, vilket inte fångas av ideal MHD. 

Place, publisher, year, edition, pages
Stockholm: KTH Royal Institute of Technology, 2025. p. ix, 74
Series
TRITA-EECS-AVL ; 2025:93
Keywords
Nuclear fusion, Tokamak, Pedestal, resistive MHD
National Category
Fusion, Plasma and Space Physics
Research subject
Electrical Engineering
Identifiers
urn:nbn:se:kth:diva-372557 (URN)978-91-8106-428-5 (ISBN)
Public defence
2025-12-09, https://kth-se.zoom.us/j/61118773378, F3, Lindstedtvägen 26, Stockholm, 10:00 (English)
Opponent
Supervisors
Note

QC 20251110

Available from: 2025-11-10 Created: 2025-11-10 Last updated: 2025-11-19Bibliographically approved

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