E. Matveeva
A5002014430- Magnetic confinement fusion research
- Fusion materials and technologies
- Laser-Plasma Interactions and Diagnostics
- Superconducting Materials and Applications
- Ionosphere and magnetosphere dynamics
- Nuclear reactor physics and engineering
- Fault Detection and Control Systems
- Gas Dynamics and Kinetic Theory
- Plasma and Flow Control in Aerodynamics
- Engineering Diagnostics and Reliability
- Advanced Theoretical and Applied Studies in Material Sciences and Geometry
- Engineering Technology and Methodologies
- Anomaly Detection Techniques and Applications
- Seismic Waves and Analysis
Czech Academy of Sciences, Institute of Plasma Physics
2017-2024
Charles University
2017-2023
The role of the COMPASS tokamak in research generation, confinement and losses runaway electron (RE) population is presented. Recently, two major groups experiments aimed at improved understanding control REs have been pursued. First, effects massive gas injection ( Ar/Ne particles) impurity seeding were studied systematically. observed phenomena include generation post-disruption RE beam current conversion from plasma to RE. Zero loop voltage was implemented order study decay simplified...
Abstract An analysis workflow has been developed to assess energy deposition and material damage for ITER vertical displacement events (VDEs) major disruptions (MD). This paper describes the use of this melt be expected during unmitigated current quench (CQ) phases VDEs MDs at different points in research plan. The plasma scenarios are modeled using DINA code with variations I p , disruption direction (upwards or downwards), Be impurity density n diffusion coefficient χ . Magnetic field line...
Abstract The understanding of the halo current properties during disruptions is key to design and operate large scale tokamaks in view thermal electromagnetic loads that they entail. For first time, we present a fully self-consistent model for simulations including neutral particles sheath boundary conditions. used simulate vertical displacement events (VDEs) occurring COMPASS tokamak. Recent experiments have shown parallel density at plasma-wall interface limited by ion saturation...
The beryllium (Be) main chamber wall interaction during a 5 MA/1.8 T upward, unmitigated VDE scenario, first analysed in [J. Coburn et al., Phys. Scr. T171 (2020) 014076] for ITER, has been re-evaluated using the latest energy deposition analysis software. Updates to DINA disruption model are summarized, including an improved numerical convergence 0D power balance, limitations on safety factor within plasma core, and choice maintain constant + halo poloidal cross-section. Such updates result...
The COMPASS tokamak at IPP Prague is a small-size device with an ITER-relevant plasma geometry and operating in both the Ohmic as well neutral beam assisted H-modes since 2012. A basic set of diagnostics installed beginning operation has been gradually broadened type diagnostics, extended number detectors collected channels improved by increased data acquisition speed. In recent years, significant progress diagnostic development motivated performance broadening its scientific programme (L-H...
Abstract The presented experimental study realized in the COMPASS tokamak demonstrates, for first time, that current density flows from plasma into vacuum vessel during disruptions is limited by ion particle flux. Such a limitation shows that, at least COMPASS, sheath forms between and wall dominates halo flow. This observation achieved measuring simultaneously saturation with negatively biased Langmuir probes grounded to vessel. These comparative measurements, which were never performed...
Abstract COMPASS addressed several physical processes that may explain the behaviour of important phenomena. This paper presents results related to main fields research obtained in recent two years, including studies turbulence, L–H transition, plasma material interaction, runaway electron, and disruption physics: Tomographic reconstruction edge/SOL turbulence observed by a fast visible camera allowed visualize turbulent structures without perturbing plasma. Dependence power threshold on...
Abstract The characterisation of plasma current quench and understanding its underlying physical processes play a crucial role when designing large fusion devices such as ITER. For the first time, an extensive analysis COMPASS tokamak disruption database is presented. A unique set magnetic diagnostics allows investigation local toroidal poloidal vessel currents, including currents flowing along open field lines from to vacuum (VV) (i.e., halo currents). Area-normalised times are in agreement...