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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…
TRIMEG-GKX: An electromagnetic gyrokinetic particle code with a piecewise field-aligned finite element method for micro- and macro-instability studies in tokamak core plasmas
Computer Physics CommunicationsThe features of the TRIMEG-GKX code are described with emphasis on the exploration using novel/different schemes compared to other gyrokinetic codes, particularly the use of object-oriented programming, filter/buffer-free treatment, and a high-order piecewi…
Ex situ investigation of boron, hydrogen, and oxygen distributions on W7-X divertor surfaces using picosecond-LIBS under vacuum
KITopenQuantitative, spatially resolved measurements of near-surface material composition on plasma-facing components (PFCs) are critical for interpreting plasma–wall interaction (PWI) driven impurity sources, assessing wall-conditioning performance, and providing…
Plasma Confinement and Nuclear Fusion
IntechOpen eBooksNuclear fusion, the process that powers stars, holds immense potential as a clean and virtually limitless energy source for humanity. Fusion research has evolved into three primary categories: thermonuclear fusion, cold fusion, and advanced fusion methods.…
Acceleration of Solvers for Plasma Simulation in the Tokamak Boundary
Open MINDSimulating turbulence in the tokamak boundary, which is crucial for understanding and optimizing future fusion power plants performance, is computationally challenging due to the complex, multi-physics, and multi-scale nature of plasma dynamics. In the boun…
How fast ions mitigate turbulence and enhance confinement in tokamak fusion plasmas
Nature Reviews Physicsnull
Ensuring the structural integrity of tokamak fusion power plants: challenges, progress and pathway
Philosophical Transactions of the Royal Society A Mathematical Physical and Engineering SciencesStructural integrity for fusion is an integrated multi-disciplinary subject spanning the science of materials, technology, engineering, health monitoring and simulation methods and algorithms for scrutinizing the assurance of reliable fusion reactor perform…
Runaway electron interactions with whistler waves in tokamak plasmas: energy-dependent transport scaling
arXiv (Cornell University)Resonant interactions between high energy runaway electrons (REs) and whistler waves are a promising mechanism for RE mitigation in tokamak plasmas. While prior studies have largely relied on quasi-linear diffusion models in simplified geometries, we presen…
A fast helium beam diagnostic at the island divertor of W7-X for the investigation of plasma edge dynamics
Repository KITopen (Karlsruhe Institute of Technology)Understanding and quantifying particle and energy transport at the plasma edge region is crucial for magnetic confinement fusion. For this purpose, a new polychromator system with 1 µs time resolution was installed for the thermal helium beam diagnostic in…
Comparative PIC-based analysis of D–T, D–He 3 , and p–B 11 fuels in channel-driven inertial fusion: Radial dynamics, hot-spot evolution, and fusion gain scaling
Europhysics Letters (EPL)Abstract Channel-driven inertial fusion offers precise control over energy deposition and hot-spot formation by guiding high-intensity ion beams through pre-formed low-density plasma channels. In this study, we present a fully PIC-enhanced comparative analy…
Multi-Timescale Dynamics Model Bayesian Optimization for Plasma Stabilization in Tokamaks
arXiv (Cornell University)Machine learning algorithms often struggle to control complex real-world systems. In the case of nuclear fusion, these challenges are exacerbated, as the dynamics are notoriously complex, data is poor, hardware is subject to failures, and experiments often…
Predictive analysis of EC wave propagation and absorption in the ADITYA-U tokamak
Physics of PlasmasThis work presents a detailed investigation of Electron Cyclotron (EC) wave propagation and absorption in the ADITYA-U tokamak using the GENRAY ray-tracing code under conditions relevant to the 42 GHz Electron Cyclotron Resonance Heating (ECRH) system. The…
Operational aspects of tritium injection into the JET tokamak
Plasma Physics and Controlled FusionAbstract The joint European torus (JET) was the only tokamak capable of deuterium–tritium (D–T) operations in the last 30 years. The first D–T operations were in the 1990s and again in 2004. In 2020/2021/2023, JET operated a much larger D–T and pure T campa…
Visualization techniques for the gyrokinetic tokamak simulation code
Frontiers in PhysicsGyrokinetic simulations of plasma microturbulence in tokamaks are challenging to visualize because the compute grid follows the magnetic field lines that spiral around the torus. We have overcome this challenge by developing three new approaches that improv…
Summary of the 29th IAEA Fusion Energy Conference under the topics materials, in-vessel components, next-step machines, and licensing and safety and socio-economic and environment
Nuclear FusionAbstract This paper represents one half of a set of two, covering the TECHNOLOGY presentations at the Fusion Energy Conference (FEC), held in London, UK, in October 2023. Dominant themes include the use of computing codes to pre-determine machine performanc…
On high-energy-density field-reversed configurations for sub-microsecond magneto-inertial fusion
Physics of PlasmasResults from theory, simulation, and experiment are presented that support the concept of sub-microsecond formation and compression of centimeter-scale field-reversed configurations (FRCs) for fusion yield. Such FRCs require 10–100+ T of applied field and a…
The quasi-continuous exhaust regime in ASDEX Upgrade and JET
Nuclear Materials and EnergyThe quasi-continuous exhaust (QCE) regime is a type-I ELM-free high confinement regime obtained at high plasma shaping and high separatrix density. A comparison with various ELM-free regimes in the literature is presented together with potential physics mod…