Javascript must be enabled to continue!
Helical mode localization and mode locking of ideal MHD instabilities in magnetically perturbed tokamak plasmas
View through CrossRef
Abstract
In H-mode tokamak plasmas, the achievable pressure-gradient is limited by type-I Edge Localized Modes (ELMs), which are projected to cause severe damage to future fusion devices. There are several approaches aiming to mitigate/suppress the occurrence of ELMs, such as the application of an external non-axisymmetric magnetic perturbation field, which breaks the axisymmetry of the tokamak plasma. In this work we use the CASTOR3D code to investigate helical localization and mode locking of edge-localized ideal MHD instabilities in rotating and flow-free magnetically perturbed tokamak plasmas with
N
P
=
2
periodicity. Helically localized instabilities are separated into two classes: quasi-locked and strictly locked. In a non-rotating plasma, the localization of quasi-locked modes is determined by an envelope while their precise location under the envelope is arbitrary, whereas strictly locked modes can only occur at a single helical position. Strictly locked modes only rotate if the toroidal plasma rotation exceeds a critical threshold; above the threshold the forced rotation of the strictly locked modes is non-uniform. For quasi-locked modes, no such critical threshold exists; they rotate uniformly beneath their envelope in the case of finite plasma rotation. The helical localization of both quasi-locked and strictly locked instabilities is determined by the energetic decomposition of the instabilities close to the most unstable flux-surface; for example, strongly current-density driven instabilities are aligned with regions of augmented parallel equilibrium current-density. Finally, we compare the computationally determined localization of MHD instabilities to experimental observations. The determined MHD instability is located at the same position as the experimentally measured modes with respect to the equilibrium corrugation, verifying that ideal MHD can describe the experimentally observed instabilities.
Title: Helical mode localization and mode locking of ideal MHD instabilities in magnetically perturbed tokamak plasmas
Description:
Abstract
In H-mode tokamak plasmas, the achievable pressure-gradient is limited by type-I Edge Localized Modes (ELMs), which are projected to cause severe damage to future fusion devices.
There are several approaches aiming to mitigate/suppress the occurrence of ELMs, such as the application of an external non-axisymmetric magnetic perturbation field, which breaks the axisymmetry of the tokamak plasma.
In this work we use the CASTOR3D code to investigate helical localization and mode locking of edge-localized ideal MHD instabilities in rotating and flow-free magnetically perturbed tokamak plasmas with
N
P
=
2
periodicity.
Helically localized instabilities are separated into two classes: quasi-locked and strictly locked.
In a non-rotating plasma, the localization of quasi-locked modes is determined by an envelope while their precise location under the envelope is arbitrary, whereas strictly locked modes can only occur at a single helical position.
Strictly locked modes only rotate if the toroidal plasma rotation exceeds a critical threshold; above the threshold the forced rotation of the strictly locked modes is non-uniform.
For quasi-locked modes, no such critical threshold exists; they rotate uniformly beneath their envelope in the case of finite plasma rotation.
The helical localization of both quasi-locked and strictly locked instabilities is determined by the energetic decomposition of the instabilities close to the most unstable flux-surface; for example, strongly current-density driven instabilities are aligned with regions of augmented parallel equilibrium current-density.
Finally, we compare the computationally determined localization of MHD instabilities to experimental observations.
The determined MHD instability is located at the same position as the experimentally measured modes with respect to the equilibrium corrugation, verifying that ideal MHD can describe the experimentally observed instabilities.
Related Results
Analysis of energetic particle-driven Alfvénic instabilities in tokamak and stellarator plasmas using three dimensional numerical tools
Analysis of energetic particle-driven Alfvénic instabilities in tokamak and stellarator plasmas using three dimensional numerical tools
In this thesis, a detailed analysis of the experientially observed energetic particle-driven Alfvénic instabilities in tokamak and stellarator plasmas using three dimensional numer...
Stabilized C1-bicubic finite element method for nonlinear MHD modeling of tokamak plasma
Stabilized C1-bicubic finite element method for nonlinear MHD modeling of tokamak plasma
Méthode d'éléments finis C1-bicubique stabilisée pour la modélisation MHD non linéaire du plasma de tokamak
Le tokamak est l’un des systèmes prometteurs mis au poin...
Magnetosphere simulations with ideal MHD, Hall MHD and the MHD with Adaptively Embedded Particle-in-Cell (MHD-AEPIC) models
Magnetosphere simulations with ideal MHD, Hall MHD and the MHD with Adaptively Embedded Particle-in-Cell (MHD-AEPIC) models
<p>The Magnetohydrodynamic with Embedded Particle-In-Cell (MHD-EPIC) model has been developed and applied successfully to Earth, Mercury, Mars and Ganymede magnetosph...
MHD control in burning plasmas
MHD control in burning plasmas
Fusion physics focuses on the complex behaviour of hot plasmas confined by magnetic fields with the ultimate aim to develop a fusion power plant. In the future generation of tokama...
The Nuclear Fusion Award
The Nuclear Fusion Award
The Nuclear Fusion Award ceremony for 2009 and 2010 award winners was held during the 23rd IAEA Fusion Energy Conference in Daejeon. This time, both 2009 and 2010 award winners w...
Indoor Localization System Based on RSSI-APIT Algorithm
Indoor Localization System Based on RSSI-APIT Algorithm
An indoor localization system based on the RSSI-APIT algorithm is designed in this study. Integrated RSSI (received signal strength indication) and non-ranging APIT (approximate pe...
A robust solution for the resistive MHD toroidal Δ′ matrix in near real-time
A robust solution for the resistive MHD toroidal Δ′ matrix in near real-time
We introduce a new near real-time solution for the tokamak resistive MHD Δ′ matrix. By extending state transition matrix methods introduced in [Glasser et al., Phys. Plasmas 25(3),...
Conceptual design and preliminary data analysis for classification of plasma disruption event at Aditya-U tokamak
Conceptual design and preliminary data analysis for classification of plasma disruption event at Aditya-U tokamak
Disruption prediction and its avoidance/mitigation is an essential part of the tokamak operations, particularly for large size tokamak as the disruptions could produce very large h...

