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On the Possibility of Parametric Excitation of Two-Dimensional Eigenmodes of Ion Bernstein Wave in ECRH Experiments at the TCV Tokamak
Plasma Physics ReportsAbstract For typical conditions of the ECRH experiments at the TCV tokamak, a new scenario of low-threshold decay of the extraordinary wave, the frequency of which corresponds to the second harmonic of electron cyclotron frequency at the axis of the plasma…
Simulations of SMBI on high-field and low-field sides of the HL-2A tokamak
Plasma Physics and Controlled FusionAbstract Enhancing plasma injection efficiency and penetration depth is crucial for achieving high-performance steady-state fusion confinement in ITER, the next generation magnetic confinement fusion device. Based on the trans-neut module within the BOUT++…
Stabilization of sawtooth instability by short gas pulse injection in ADITYA-U tokamak
Physical Review ResearchExperiments 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 then leads to an incre…
Feasibility of Negative Triangularity Equilibria in the SPARC Tokamak
arXiv (Cornell University)We investigate the feasibility of negative triangularity (NT) plasma configurations in the SPARC tokamak, a compact, high-field device (up to 12.2 T) designed for positive triangularity (PT) operation. Using the FreeGS free-boundary equilibrium solver, we s…
Edge radial electric field in positive and negative triangularity plasmas in the TCV tokamak
Nuclear FusionAbstract We present the first edge E r measurements in negative triangularity (NT) plasmas in the Tokamak à Configuration Variable (TCV). The Doppler backscattering measurements of v ⊥ ≈ E r / B reveal a significant impact of triangularity on the E r well:…
Hermes-3 simulation of the low-n X-point mode driven by impurity in tokamak edge plasmas
Nuclear Materials and EnergyHermes-3, a multi-fluid plasma simulation tool is applied to investigate the low-n X-point mode driven by coupling between drift wave and impurity radiation condensation instability in tokamak edge plasmas. The radiation loss function of impurities under no…
Initial lower hybrid current drive experiments with a passive active multijunction launcher in the ADITYA-U tokamak
Plasma Physics and Controlled FusionAbstract Following the successful integration of a 3.7 GHz, 250 kW-1s passive active multijunction (PAM) launcher in the ADITYA-U tokamak, lower hybrid (LH) current drive experiments were conducted for the first time. The launcher was designed to launch low…
High-throughput full-f gyrokinetics of the tokamak boundary
arXiv (Cornell University)Full-f global gyrokinetic simulations of the plasma boundary have until now required heroic computational efforts and case-by-case expert intervention, precluding systematic parameter scans. Here we demonstrate a paradigm shift: hundreds of independent, con…
Overview of recent progress for high power and long pulse operation of ICRF heating system in EAST Tokamak
Plasma Physics and Controlled FusionAbstract 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…
Modelling and inversion of bremsstrahlung from runaway electrons on the GOLEM tokamak
Plasma Physics and Controlled FusionAbstract 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…
Absolute parametric decay instabilities in ECRH experiments and their possible role in the missing power effect at the T-10 tokamak
Physics of PlasmasThe 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…
Constructing field-aligned coordinate systems for gyrokinetic simulations of tokamaks in X-point geometries
Journal of Plasma PhysicsStructures 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,…
High-Spatiotemporal-Resolution Hard-X-Ray Diagnostic System on NanChang Spherical Tokamak
Fusion Science & TechnologyThe 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…
Spherical tokamak physics research in preparation for the operation of NSTX-U
Nuclear FusionAbstract 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…
Neutral particle analyzer for plasma diagnostics on tokamak ST40
Review of Scientific InstrumentsA 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…
Self-consistent plasma-neutrals fluid modeling of edge and scrape-off layer turbulence in diverted tokamaks
Plasma Physics and Controlled FusionAbstract 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…
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…
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…
Counter-propagating toroidal Alfvén eigenmodes in tokamaks
Nuclear FusionAbstract 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…
First simultaneous observation of co- and counter-current fast-ion losses in the ASDEX Upgrade tokamak
Nuclear FusionAbstract 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…
Ripple loss parametrization during ICRH in the WEST tokamak
Nuclear FusionAbstract 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…
High-resolution visible spectroscopy for ion temperature and flow velocity measurements of the TCV divertor plasma
Review of Scientific InstrumentsA 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…
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…
Engineering concept of the VNS - a beam-driven tokamak for component testing
Fusion Engineering and DesignThe 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…