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Breakthrough in China’s fusion energy: HL-3 tokamak achieves high ion temperature and fusion triple product
The InnovationControlled nuclear fusion represents the holy grail of clean energy, offering a nearly limitless power source with minimal environmental impact: China’s HL-3 tokamak, a key experimental device in the country’s fusion program.1,2 The deuterium-trillium (DT)…
Thermal modeling of runaway electron induced damage in the SPARC tokamak
Plasma Physics and Controlled FusionAbstract The integrity of plasma-facing components (PFCs) in tokamaks is critically challenged by transient events such as runaway electron (RE) impacts. We report the first systematic analysis of the thermal damage to tungsten-based PFC tiles comprising th…
Disruption mitigation modeling for the SPARC tokamak
Physics of PlasmasTwo primary systems planned for disruption mitigation in the SPARC tokamak, massive gas injection (MGI), and the runaway electron mitigation coil (REMC), are modeled with the 3D MHD code NIMROD. MGI is modeled in four configurations, and each of the 6-valve…
Suppression of tearing modes by External Rotational Transform in a Tokamak-Stellarator hybrid configuration on J-TEXT
Nuclear FusionAbstract A Tokamak-Stellarator hybrid configuration has been established on the J-TEXT tokamak by the application of stellarator-like External Rotational Transform (ERT) coils. The hybrid configuration aims to combine the advantages of both tokamak and stel…
Inertial Fusion Energy (IFE) at the 2025 IAEA Fusion Energy Conference
Nuclear FusionAbstract The paper provides a high-level summary of the contributions given at the 30th International Atomic Energy Agency Fusion Energy Conference (FEC2025) held in Chengdu, China, from the 13th to the18th of October, 2025, under the category ‘Inertial Fus…
Performance and transport in the ARC tokamak
Journal of Plasma PhysicsThe ARC $^{\textrm {TM}}$ tokamak, a high-field ( $B_T$ = 11.4 T) fusion power plant, under development by Commonwealth Fusion Systems, is studied using a suite of integrated modelling tools to predict its fusion power generation ( $P_{fus}$ ), transport an…
A multi-purpose reciprocating probe drive system for studying the effect of gas-puffs on edge plasma dynamics in the ADITYA-U tokamak
AIP AdvancesThis article reports the development of a versatile high-speed reciprocating drive system (HRDS) with interchangeable probe heads to characterize the edge plasma region of the ADITYA-U tokamak. The system is driven by a servo motor, which is controlled by a…
Diagnostics: Chapter 8 of the special issue: on the path to tokamak burning plasma operation
Nuclear FusionAbstract This chapter presents the activity conducted by the ITPA topical group (TG) on Diagnostics over about the last 15 years. Following a general introduction of the ITER Diagnostics led by their measurement roles, the document is organized in several s…
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…