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Electromagnetic Gyrokinetic Simulation of Tokamak Plasma with Semi-Lagrangian Scheme
Communications in Computational PhysicsThe re-splitting $δf$ method (Ye et. al CPC 2020) has been implemented into the global semi-Lagrangian gyrokinetic code NLT (Lei Ye et al. 2016, JCP) for the simulations of electromagnetic micro-turbulence in tokamak plasmas. The re-splitting method can be…
A comparison of low-n Mercier unstable Wendelstein stellarators and quasi-interchange modes in tokamaks
Journal of Plasma PhysicsMercier’s criterion is typically enforced as a hard operational limit in stellarator design. At the same time, past experimental and numerical studies have shown that this limit may often be surpassed, though the exact mechanism behind this nonlinear stabil…
Achieving efficient implosion for double-shell targets driven by Z-pinch dynamic hohlraum
Physics of PlasmasDouble-shell targets offer significant advantages in ignition margins and energy gain. We conducted theoretical studies and radiation hydrodynamic simulations to achieve efficient implosion of the double-shell targets driven by Z-pinch dynamic hohlraum (ZPD…
Hybrid hydrogen-electricity production using spherical tokamaks: a cost-driver sensitivity study and techno-economic analysis
Nuclear FusionAbstract Hybrid fusion power plants, which produce both hydrogen and electricity, are proposed as a way to decarbonise the fossil-fuel-dominated primary energy market and improve plant economics. The main cost drivers of a fusion power plant based on a sphe…
First Experiments with Ion Cyclotron Heating at the Spherical Tokamak Globus-M2
Plasma Physics ReportsAbstract On the Globus-M2 spherical tokamak, experiments on ion cyclotron resonance heating (ICRH) of plasma were conducted in discharges with a toroidal magnetic field above 0.7 T under conditions of Ohmic-only heating and additional heating by a neutral b…
Coupled 2D MHD and runaway electron fluid simulations of SPARC disruptions
Physics of PlasmasRunaway electrons (REs) generated during disruption events in tokamaks can carry mega-Ampère level currents, potentially causing damage to plasma-facing components. Understanding RE evolution during disruption events is important for evaluating strategies t…
Influence of 3D helical magnetic perturbations on runaway electron generation in J-TEXT tokamak
Plasma Science and TechnologyAbstract A large number of runaway electrons (REs) generated during disruption can cause significant damage to next-generation large-scale tokamaks. The influence of three-dimensional (3D) helical magnetic perturbations on the suppression of RE generation w…
Feasibility of a Flexible, Hybrid Tokamak-Stellarator Experiment using an Axisymmetric Dipole Coil Array
arXiv (Cornell University)We demonstrate the design of a flexible, university-scale hybrid tokamak-stellarator experiment based on an axisymmetric array of planar HTS dipole coils. Because the coil array has few geometric degrees of freedom, we use single-stage optimization of the c…
Beyond power gain: Toward a comprehensive milestone framework for all fusion energy concepts
Physics of PlasmasIn this Perspective paper, we propose an inclusive set of milestone categories to track the progress of fusion concepts from scientific research through grid-connected electricity. We emphasize the importance of not only (1) plasma performance but also (2)…
Conceptual studies for the EU-DEMO EC heating system transmission line
Fusion Engineering and DesignThe Electron Cyclotron (EC) Heating system for the EU-DEMO tokamak, designed within the EUROfusion consortium activities as a device to demonstrate the feasibility of a Fusion Reactor, will inject power in different plasma locations to provide a series of t…
Application of Nuclear Safety Culture in Fusion Energy: A Case Study of the Korean ITER Project
IEEE Transactions on Plasma ScienceRecently, strategic partnerships between public and private sectors have increased in the field of fusion energy, aiming to achieve the commercial feasibility of fusion-generated electricity by the 2030s. Therefore, fostering a positive nuclear safety cultu…
Divertor shaping with neutral baffling as a solution to the tokamak power exhaust challenge
Communications PhysicsExhausting power from the hot fusion core to the plasma-facing components is one fusion energy’s biggest challenges. The MAST Upgrade tokamak uniquely integrates strong containment of neutrals within the exhaust area (divertor) with extreme divertor shaping…
Global gyrokinetic simulations of kinetic ballooning mode in NSTX-U plasmas
Nuclear FusionAbstract Understanding the kinetic ballooning mode (KBM) is crucial for optimizing plasma performance in high- β spherical tokamaks. Global gyrokinetic simulations of KBMs in a projected NSTX-U shot are presented using realistic magnetic geometry and plasma…
Magnetic mesh generation and field line reconstruction for scrape-off layer and divertor modeling in stellarators
Plasma Physics and Controlled FusionAbstract The design of divertor targets and baffles for optimal heat and particle exhaust from magnetically confined fusion plasmas requires a combination of fast, low-fidelity models (such as EMC3-Lite (Feng 2022 Plasma Phys. Control. Fusion 64 125012)) fo…
Double 3 MJ dense plasma focus for thermonuclear drive inertial confinement fusion
Scientific ReportsNuclear fusion remains one of the most promising solutions for clean and sustainable energy production. However, significant challenges-including energy losses, plasma instabilities, and high operational costs-continue to hinder its practical realization. W…
A dynamic model of a power conversion system with indirect thermal energy storage for a pulsed fusion tokamak for use in design optimisation
Fusion Engineering and DesignThis work addresses the challenge of designing a power conversion system, which converts thermal energy into electrical energy, that can handle heat generation from a pulsed fusion tokamak. Large transients would be damaging for components such as turbomach…
Development and initial operation of the ICRF system on the J-TEXT tokamak
Plasma Science and TechnologyAbstract A two-chain ion cyclotron range of frequency (ICRF) system has been developed and commissioned on the J-TEXT tokamak, with the primary objective of establishing a controllable experimental platform for systematic studies of antenna–plasma coupling…
Overview of the third JET deuterium-tritium campaign
Plasma Physics and Controlled FusionAbstract JET returned to deuterium-tritium operations in 2023 (DTE3 campaign), approximately two years after DTE2. DTE3 was designed as an extension of JET’s 2022-2023 deuterium campaigns, which focused on developing scenarios for ITER and DEMO, integrating…
Resistive hose modes in tokamak runaway electron beams II
Physics of PlasmasResistive hose instabilities of runaway electron (RE) beams immersed in resistive background plasmas are examined with analytic and numerical calculations. The RE beam-plasma equilibria considered are characteristic of the situation observed post-thermal qu…
Planar coil design for the Helios stellarator fusion power plant
Fusion Engineering and DesignA new candidate coil set for Thea Energy, Inc.’s quasi-axisymmetric fusion power plant, “Helios”, is discussed. Every coil is planar and convex. The coil set consists of 12 encircling coils that link the plasma to generate net toroidal flux, and 324 shaping…
60 years of science in ICF: from conception to scientific breakeven on the National Ignition Facility
Reviews of Modern Plasma PhysicsAbstract The recent achievements of a burning plasma, fusion ignition, and scientific energy gain with deuterium-tritium (DT) fuel at Lawrence Livermore National Laboratory’s National Ignition Facility (NIF) represents a major milestone in the development o…
Evaluation of neutron local shielding for electronics in accelerators and tokamaks using FLUKA
Open MINDIn high-energy particle accelerators and fusion tokamaks, Commercial Off-The-Shelf (COTS) electronics must withstand neutron-dominated radiation fields that threaten their reliability. Within the Neutron Electronics Reliability In Tokamaks and Accelerators…
Characterization at 4 K of FXM-19 forged products for their use in fusion energy
IOP Conference Series Materials Science and EngineeringAbstract Driven by the electrification of industries and economic, the global demand for electricity is anticipated to rise in the coming decades. In this framework there is a growing interest in fusion energy devices as a sustainable energy solution. Among…
SOLPS-ITER modelling of helium transport, recycling and pumping at the ASDEX Upgrade tokamak
Nuclear FusionAbstract Extrapolating the observed behavior of helium exhaust in current tokamaks towards future reactors requires the understanding of the underlying physical mechanisms determining helium transport, recycling and pumping. Helium compression is the main p…