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技术文档在线预览

Overview of recent progress for high power and long pulse operation of ICRF heating system in EAST Tokamak

Plasma Physics and Controlled Fusion

Abstract Significant advancements have been achieved in facilitating high-power and long-pulse operation up to 310 s by developing novel techniques for ion cyclotron range of frequency (ICRF) wave heating systems on EAST. This paper presents an overview of…

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Modelling and inversion of bremsstrahlung from runaway electrons on the GOLEM tokamak

Plasma Physics and Controlled Fusion

Abstract Runaway electron (RE) losses are usually diagnosed with a small number of hard x-ray (HXR) detectors, which provide limited spatial information. Although multi-chord HXR spectrometers on large devices allow reconstruction of RE parameters in the pl…

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Absolute parametric decay instabilities in ECRH experiments and their possible role in the missing power effect at the T-10 tokamak

Physics of Plasmas

The possibility of excitation of absolute parametric decay instabilities in X2- and O1-mode electron cyclotron resonance heating experiments with monotonic density profile and their possible consequences for the EC absorption efficiency under conditions of…

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Constructing field-aligned coordinate systems for gyrokinetic simulations of tokamaks in X-point geometries

Journal of Plasma Physics

Structures in tokamak plasmas are elongated along the direction of the magnetic field and short in the directions perpendicular to the magnetic field. Many tokamak simulation codes take advantage of this by using a field-aligned coordinate system. However,…

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High-Spatiotemporal-Resolution Hard-X-Ray Diagnostic System on NanChang Spherical Tokamak

Fusion Science & Technology

The high-spatiotemporal-resolution hard-X-ray diagnostic on the NanChang Spherical Tokamak (NCST) for fast electron research is presented. The 31 detectors of diagnosis are all composed of a lutetium yttrium oxyorthosilicate crystal coupled silicon photomul…

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Spherical tokamak physics research in preparation for the operation of NSTX-U

Nuclear Fusion

Abstract The National Spherical Torus Experiment Upgrade (NSTX-U) is preparing to resume operation, representing a crucial step toward realizing compact, cost-effective fusion pilot plants. In advance of this, extensive modeling and data analysis have been…

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Neutral particle analyzer for plasma diagnostics on tokamak ST40

Review of Scientific Instruments

A neutral particle analyzer was designed and implemented for plasma diagnostics on the spherical tokamak ST40. The diagnostic aims to measure both the bulk ion temperature (0.5-10 keV) and the energy distribution of fast ions generated by a neutral beam inj…

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Self-consistent plasma-neutrals fluid modeling of edge and scrape-off layer turbulence in diverted tokamaks

Plasma Physics and Controlled Fusion

Abstract We report on developments in the edge and scrape-off layer turbulence code GRILLIX to self-consistently simulate plasma turbulence coupled to a fluid neutral gas model. The neutrals model is extended from a single fluid moment (neutrals density) to…

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Stabilization of sawteeth instability by short gas pulse injection in ADITYA-U tokamak

arXiv (Cornell University)

Experiments on ADITYA-U tokamak show a marked enhancement in the sawtooth period by application of short gas puffs of fuel that cause a modification of the radial density profile. A consequent suppression of the trapped electron modes (TEMs) then leads to a…

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Lithium Droplet Transport in Tokamak Edge Plasmas

arXiv (Cornell University)

A lithium droplet transport and evaporation model has been developed within the Direct Simulation Monte Carlo code OpenEdge. This model integrates gravity, collisional ion drag, orbital-motion-limited charging, energy-balance evaporation, and an anisotropic…

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Counter-propagating toroidal Alfvén eigenmodes in tokamaks

Nuclear Fusion

Abstract Mechanisms of destabilization of toroidal Alfvén eigenmodes (TAEs) in tokamaks are analyzed with the aim to reveal those leading to modes propagating in the direction opposite to plasma current, i.e. counter-propagating modes (ctr-TAE). Plasmas wit…

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First simultaneous observation of co- and counter-current fast-ion losses in the ASDEX Upgrade tokamak

Nuclear Fusion

Abstract In ITER and future fusion power plants, the source of the fusion born alpha particles is almost isotropic in pitch angle, thus having co- and counter-current populations. For trapped ions, the co-current side of the orbit corresponds to its outer l…

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Ripple loss parametrization during ICRH in the WEST tokamak

Nuclear Fusion

Abstract The Ion Cyclotron Resonance Heating (ICRH) system is one of the primary additional heating methods in the WEST tokamak, playing a significant role in achieving high-performance plasmas. The European Transport Simulator provides valuable insights in…

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High-resolution visible spectroscopy for ion temperature and flow velocity measurements of the TCV divertor plasma

Review of Scientific Instruments

A high-resolution spectroscopic system was installed on the Tokamak à Configuration Variable (TCV), whose toroidal lines-of-sight (LOS) cross the divertor region. This system simultaneously measures the Doppler broadening and Doppler shift of several spectr…

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Effect of LH and ECR waves on plasma parameters in ADITYA Upgrade tokamak

arXiv (Cornell University)

The plasma discharges in ADITYA Upgrade Tokamak are produced by means of transformer action, in which Ohmically created plasma is driven by means of a secondary loop voltage. Due to reduction of plasma resistivity after a certain level of plasma temperature…

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Engineering concept of the VNS - a beam-driven tokamak for component testing

Fusion Engineering and Design

The qualification of in-vessel components for a fusion power plant requires a test environment with a high flux of 14 MeV neutrons over a sufficiently large surface and volume. Performance testing and qualification of the complex design and technologies of…

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Optimization of the magnetic difference calibration method on Huan Liu-3 tokamak

Review of Scientific Instruments

Blackbody in situ calibration is a standard method for Electron Cyclotron Emission (ECE) diagnostics but involves complex in-vessel hardware that poses maintenance challenges. To provide a robust relative calibration strategy, the Magnetic Difference Calibr…

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The impact of non-local parallel electron transport on plasma-impurity reaction rates in tokamak scrape-off layer plasmas

Plasma Physics and Controlled Fusion

Abstract Plasma-impurity reaction rates are a crucial part of modelling tokamak scrape-off layer (SOL) plasmas. To avoid calculating the full set of rates for the large number of important processes involved, a set of effective rates are typically derived w…

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Gramian Analysis of Tokamak Electromagnetic Field Profiles in a Port-Hamiltonian Model

IEEE Transactions on Plasma Science

We perform a finite-horizon controllability and reachability analysis of tokamak electromagnetic field profiles using a 0-D resistive-diffusion model in the port-Hamiltonian (PH) framework. With a quadratic Hamiltonian, the PH dynamics reduce to a linear re…

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Initial results of hard X-ray spectroscopy by LaBr (Ce) detector for runaway electron study at the HL-3 tokamak

Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment

null

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Public Perspectives on the Design of Fusion Energy Facilities: Evidence from a Participatory Design Workshop and Recommendations for Technology Developers

Journal of Fusion Energy

Abstract As fusion energy technologies approach demonstration and commercial deployment, understanding public perspectives on future fusion facilities will be critical for achieving social license. In a departure from the ‘decide-announce-defend’ approach t…

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An OpenMC model of the SPARC tokamak for the diagnostic scoping studies

Fusion Engineering and Design

null

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First microsecond velocity-space resolved simultaneous measurements of co- and counter-current fast-ion losses in forward and reverse magnetic field in a tokamak

Nuclear Fusion

Abstract A novel Fast Ion Loss Detector was designed, manufactured, installed and commissioned at the Tokamak á Configuration Variable. This is the first Fast Ion Loss Detector to feature four collimators that enable simultaneous detection of co- and counte…

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Quasi-optical characterization and preliminary experimental results of electron cyclotron emission imaging on HL-3 tokamak

Plasma Science and Technology

Abstract Electron cyclotron emission imaging (ECEI) is a critical diagnostic tool for measuring two-dimensional electron temperature fluctuations. The optical system, a key component of the ECEI diagnostic, determines the spatial resolution, field of view,…

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