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Variability of MHD instabilities in benign termination of high-current runaway electron beams in the JET and DIII-D tokamaks
Nuclear FusionAbstract Benign termination, in which magnetohydrodynamic (MHD) instabilities deconfine runaway electrons (REs) following hydrogenic injections, is a promising strategy for mitigating dangerous RE loads after disruptions. Recent experiments on the Joint Eur…
Stellaris: A high-field quasi-isodynamic stellarator for a prototypical fusion power plant
Fusion Engineering and DesignMagnetic confinement fusion research has so far prioritized the tokamak concept, which presents greater design simplicity at the cost of control complexity in comparison to stellarators. Recent progress on high-temperature superconductors (HTS) has enabled…
Laser-based inertial fusion energy system enabled by optical enhancement cavities and a direct-drive configuration reactor
Optics ExpressWe propose a novel and highly efficient laser inertial fusion energy reactor concept based on the shock ignition scheme, in which laser-plasma instabilities are mitigated through 500-beam, multicolor, slowly rotating polarization laser beam irradiation. The…
Advanced Structural Assessment of a Bucked-and-Wedged Configuration for the EU DEMO Tokamak Under a 16.5 T Magnetic Field
EnergiesThe pursuit of compact and efficient fusion energy systems necessitates innovative structural concepts capable of withstanding extreme operational conditions. This study presents a preliminary structural evaluation and stress assessment of a bucked-and-wedg…
Introduction and overview: Chapter 1 of the special issue: on the path to tokamak burning plasma operation
Nuclear FusionAbstract The International Tokamak Physics Activity (ITPA) has developed a comprehensive overview of the results of its coordinated R&D activities in fusion physics and diagnostics implemented during the past two decades with the aim of developing an improv…
Hybrid kinetic-MHD modeling of alpha-driven TAEs in the SPARC tokamak
Nuclear FusionAbstract As the magnetic confinement fusion community prepares for the next generation of fusion devices and burning plasmas, there is still a question of whether fast ions (FIs) will drive MHD instabilities, causing significant redistribution or even loss…
Integrated modelling of tokamak plasmas: progress and challenges towards ITER operation and reactor design
Plasma Physics and Controlled FusionAbstract In tokamak plasmas, non-linear interplay between transport and sources/sinks takes place for all transported quantities (current, heat, particles and momentum). Thanks to integrated modelling frameworks, we can iterate physics-based quasilinear tur…
Optimization of buildable stellarator coils to confine electron-positron plasmas and advance fusion reactor design
Elektronische Hochschulschriften der LMU München (Ludwig-Maximilians-Universität München)The stellarator is considered a front-runner for a future fusion power plant. Unlike axisymmetric magnetic confinement fusion devices like tokamaks, stellarators ely on complex, numerically optimized three-dimensional magnetic fields to confine the plasma,…
Numerical investigation of liquid wall ablation in inertial fusion energy chambers
Nuclear FusionAbstract This paper presents a novel approach for modeling liquid wall ablation in liquid wall-protected inertial fusion energy (IFE) chambers. These systems are promising candidates for the implementation of fusion technology, yet significant gaps remain i…
The dual-electron cyclotron emission based measurement of 3D structures on DIII-D tokamak
Plasma Physics and Controlled FusionAbstract The measurements of the locked mode and other 3D magnetohydrodynamic modes are essential for real-time control of plasma stability in future fusion reactors. Current magnetic measurements present non-negligible challenges for the application on fus…
Inaugural central fueling experiment with Compact Torus in EAST
Nuclear FusionAbstract We report, for the first time, non-disruptive central fueling experiments utilizing Compact Torus (CT) plasma injection in the medium-sized fully-superconducting tokamak, EAST ( R 0 = 1.9 m, a = 0.45 m, B t = 1.5–2.5 T). In these experiments, the C…
Design of an X-point slot closed divertor for the HL-3 tokamak with SOLPS-ITER
Nuclear FusionAbstract In this paper, we introduce a novel X-point Slot Closure (XSC) divertor developed for the HL-3 tokamak. The XSC divertor combines the benefits of W-shaped, V-shaped, Small Angle Slot, and Compact Radiative Divertor divertors into a compact design t…
An electromagnetic model in SOLEDGE3X for edge plasma turbulence simulations in tokamaks
Journal of Computational PhysicsEven small fluctuations in the magnetic field are known to impact edge plasma turbulence and transport properties in magnetic confinement fusion devices. Magnetic induction modifies the parallel electric field, and as such, it impacts the parallel current i…
Overview of the Helios Design: A Practical Planar Coil Stellarator Fusion Power Plant
arXiv (Cornell University)Thea Energy, Inc. has developed the preconceptual design for "Helios," a fusion power plant based on the planar coil stellarator architecture. In this overview paper, the design is summarized and the reader is referred to the other papers for more detail. T…
An availability-centric Q-metrics framework for assessing fusion power-plant engineering viability
Fusion Engineering and DesignAs fusion development advances toward DEMO and a first-of-a-kind power-plant, engineering operability and availability increasingly dominate overall system performance. Plasma physics gain metrics, such as Q PHYSICS , demonstrate scientific feasibility but…
Investigating dynamic scenarios of a spherical tokamak fusion power plant
Fusion Engineering and DesignSpherical Tokamak for Energy Production (STEP) is a programme led by the United Kingdom Atomic Energy Authority (UKAEA) to design and build a fusion energy power plant that can demonstrate net electricity generation. One of the unique challenges of the STEP…
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…