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Magnetohydrodynamic instability modulated runaway electron losses in the ADITYA-U tokamak
Nuclear FusionAbstract In the ADITYA-U tokamak, modulation in the Hard x-ray (HXR) emission from the limiter synchronous with a m/n = 2/1 tearing mode is observed during the flat-top and pre-disruption phases of a discharge with a significant runaway electron (RE) popula…
Effect of magnetic islands on fast ions in Wendelstein 7-X and ASDEX Upgrade
Open MINDThis thesis investigates the effects of magnetic islands on the fast ions in tokamak and stellarator configurations, utilizing numerical modeling and validation against experimental data. Magnetic islands can occur in fusion plasmas due to internal or exter…
Multi-Agent Design Assistant for the Simulation of Inertial Fusion Energy
arXiv (Cornell University)Inertial fusion energy promises nearly unlimited, clean power if it can be achieved. However, the design and engineering of fusion systems requires controlling and manipulating matter at extreme energies and timescales; the shock physics and radiation trans…
Modelling of electron cyclotron energy gain in the tokamak pre-ionization phase
Nuclear FusionAbstract This work presents a model for predicting electron energy gain from electron cyclotron (EC) wave–particle interactions during the breakdown phase of tokamak pre-ionization. Investigation of this phase to infer the EC requirements inevitably demands…
Quasi-Periodic Mitigation of Runaway Electron Beam via Interaction with Kinetic Instabilities in the QUEST Spherical Tokamak
Plasma and Fusion ResearchRunaway electron (RE) driven kinetic instabilities have been observed in the QUEST spherical tokamak. A strong correlation between decay of the plasma current and activity of kinetic instabilities was first found with quasi-periodic behaviour during current…
Integrated operation scenarios: Chapter 6 of the special issue: on the path to tokamak burning plasma operation
Nuclear FusionAbstract Here we report the progress of the development and optimization of operational scenarios for ITER and beyond, focusing upon baseline, hybrid, and steady-state scenarios since 2007. This includes advancements made by the integrated operation scenari…
SPARC Tokamak Error Field Expectations and Physics-Based Correction Coil Design
arXiv (Cornell University)Non-axisymmetric magnetic field coils have been designed to provide efficient error field correction and suppress edge localized modes in SPARC - a compact high-field tokamak that is presently under construction at Commonwealth Fusion Systems. These designs…
Geodesic extended modes in low magnetic shear tokamaks and stellarators
arXivTheories of ion-scale microinstabilities in tokamaks and stellarators typically assume that the passing electrons respond adiabatically due to their fast propagation speed. However, when the magnetic shear becomes sufficiently small, ion-scale modes can ext…
Feature issue introduction: laser driven inertial confinement fusion and bridging the gaps to inertial fusion energy systems
Optics ExpressMajor fusion research milestones have been achieved using laser driven inertial confinement fusion (ICF) in recent years, and these successes have ignited tremendous enthusiasm for inertial fusion energy (IFE). However, the complexity and difficulty of obta…
Mechanical model for a full fusion tokamak enabled by supercomputing
Nuclear FusionAbstract Determining stress and strain in a component of a fusion power plant involves defining boundary conditions for the mechanical equilibrium equations, which implies the availability of a full reactor model for defining those conditions. To address th…
Propagation of ion cyclotron emission in the DIII-D tokamak
Physics of PlasmasExperiments in L- and H-mode plasmas performed on the DIII-D tokamak explored ion cyclotron emission (ICE) propagation via the recently upgraded ICE diagnostic. The distance between the plasma and the outer wall was scanned to alter the evanescent region, w…
The Divertor Tokamak Test facility research plan
Nuclear FusionAbstract The Divertor Tokamak Test facility (DTT) is a device presently under construction at the ENEA site in Frascati (Italy) in the framework of a joint public/private partnership. It has been designed as a superconducting tokamak with breakeven class pe…
Reduced modelling of scrape-off losses of runaway electrons during tokamak disruptions
Journal of Plasma PhysicsAccurate modelling of runaway electron generation and losses during tokamak disruptions is crucial for the development of reactor-scale tokamak devices. In this paper, we present a reduced model for runaway electron losses due to flux surface scrape-off cau…
A programmable stellarator-tokamak hybrid for million-scale magnetic-configuration discovery
arXivTokamaks and stellarators are the leading magnetic-confinement concepts for fusion, but they rely on complementary design principles. Tokamaks use simple axisymmetric coils and plasma current, whereas stellarators use externally generated three-dimensional…
Robustness of inertial fusion energy relevant implosions to low-mode asymmetries
Physics of PlasmasInertial confinement fusion implosions for power production need to be robust. Degradation sources need to be understood and considered for an economic power plant. In this work, the impact of low-mode asymmetries on yield is studied using 2D radiation hydr…
Parametric Tokamak Maintainability Design Evaluation
IEEE Transactions on Plasma ScienceThe system design models of tokamak fusion reactors can be parameterized and coupled to enable holistic code-based exploration and optimization of tokamak geometry. System codes have been developed for the major systems of the tokamak; however, some systems…
Generation of field-reversed configurations via neutral beam injection
Nature CommunicationsWe report evidence of successful generation of field-reversed configuration plasmas by neutral beam injection. This is achieved by trapping the steady-state beams in an initial seed plasma, hence providing a direct source of toroidally directed energetic io…
Investigating the influence of divertor baffles on nitrogen-seeded detachment in TCV with SOLPS-ITER simulations and TCV experiments
Nuclear FusionAbstract Plasma edge simulations with the SOLPS-ITER code are performed to study the influence of divertor baffles on nitrogen-seeded detachment in Tokamak à Configuration Variable (TCV) single-null, L-mode discharges. Scans of nitrogen seeding rate are con…
Effect of 4.6 GHz LHW on tungsten transport in NBI dominant H-mode plasma in EAST tokamak
Nuclear FusionAbstract Experimental observations in EAST tokamak have revealed a notable suppression of tungsten accumulation during the lower hybrid wave (LHW) injection in the neutral beam injection (NBI)-heated H-mode plasma. The variation in tungsten concentration du…
Expanding ASTRA: a unified framework for tokamak and stellarator transport modelling
Plasma Physics and Controlled FusionAbstract We present recent developments to the one-dimensional transport solver ASTRA, which will enable the simulation of plasma evolution in both tokamaks and stellarators. To achieve this, a generic current diffusion equation for the poloidal magnetic fl…
Two-photon polymerization for inertial fusion energy target fabrication
Applied Physics AAbstract This study focuses on optimizing the fabrication of foam targets for laser-driven inertial fusion energy using two-photon polymerization (2PP). 2PP offers nanoscale precision, enabling the fabrication of foams with precise control over structure, s…
Bayesian experimental design of magnetic diagnostics on the WEST tokamak
Plasma Physics and Controlled FusionAbstract Next-generation fusion reactors such as DEMO pose significant challenges in the design of diagnostic systems due to stringent spatial limitations and cost constraints. In response to these challenges, we apply Bayesian experimental design methodolo…
Experimental observation and edge characteristics of EDA H-mode on the HL-3 tokamak
Nuclear FusionAbstract The enhanced D α (EDA) H-mode features high energy confinement together with the absence of edge localized modes (ELMs) and impurity accumulation, making it highly attractive for fusion reactors. The EDA H-mode has been observed recently in the HL-…
Plasma heat load in the toroidal gaps of the ITER-like plasma facing units in WEST tokamak
Nuclear Materials and Energy• Heat loading into toroidal gap between ITER-grade PFUs. • The very high spatial resolution (0.1 mm/px) infrared camera of WEST has been used to monitor the temperature distribution. • The experimental IR images exhibit complex pattern with strong signal i…