A5082599220- Magnetic confinement fusion research
- Fusion materials and technologies
- Ionosphere and magnetosphere dynamics
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Laser-Plasma Interactions and Diagnostics
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Atomic and Subatomic Physics Research
- Plasma Diagnostics and Applications
- Nuclear Physics and Applications
- Fault Detection and Control Systems
- X-ray Spectroscopy and Fluorescence Analysis
- Viral Infections and Vectors
- High-pressure geophysics and materials
- Solar and Space Plasma Dynamics
- Spacecraft and Cryogenic Technologies
- Anomaly Detection Techniques and Applications
- Quantum and electron transport phenomena
- Scientific Computing and Data Management
- Photocathodes and Microchannel Plates
- GNSS positioning and interference
- Particle Accelerators and Free-Electron Lasers
- Advancements in Photolithography Techniques
- Scientific Measurement and Uncertainty Evaluation
Czech Academy of Sciences, Institute of Plasma Physics
2016-2025
Institut de Recherche sur la Fusion par Confinement Magnétique
2024
CEA Cadarache
2024
Culham Science Centre
2021-2024
Culham Centre for Fusion Energy
2024
Charles University
2015-2021
Czech Technical University in Prague
2021
National Centre for Nuclear Research
2021
National Agency for New Technologies, Energy and Sustainable Economic Development
2020
Royal Military Academy
2020
This paper summarizes the status of COMPASS tokamak, its comprehensive diagnostic equipment and plasma scenarios as a baseline for future studies. The former COMPASS-D tokamak was in operation at UKAEA Culham, UK 1992–2002. Later, device transferred to Institute Plasma Physics Academy Sciences Czech Republic (IPP AS CR), where it installed during 2006–2011. Since 2012 has been full with Type-I Type-III ELMy H-modes base scenario. enables together ITER-like shape flexible NBI heating system...
COMPASS Upgrade is a new medium size, high magnetic field tokamak (R = 0.9 m, Bt 5 T, Ip 2 MA) currently under design in the Czech Republic. It will provide unique capabilities for addressing some of key challenges plasma exhaust physics, advanced confinement modes and configurations as well testing facing materials liquid metal divertor concepts. This paper contains an overview preliminary engineering main systems (vacuum vessel, central solenoid poloidal coils, toroidal support structure,...
Abstract This paper reports the first experiment carried out in deuterium–tritium addressing integration of a radiative divertor for heat-load control with good confinement. Neon seeding was time D–T plasma as part second campaign JET its Be/W wall environment. The technical difficulties linked to re-ionisation heat load are reported T and D–T. compares impact neon on plasmas their D counterpart detachment, localisation radiation, scrape-off profiles, pedestal structure, edge localised modes global
Plasma Observatory (PO) is an ESA mission proposal to study for the first time plasma transport and energization in near-Earth environment simultaneously at both fluid ion scales, with a constellation of 7 spacecraft: 1 mother 6 daughters. In PO framework, MAG-M proposed fluxgate magnetometer onboard Mothercraft, be built Imperial College London.It dual-sensor instrument mounted on rigid boom dedicated high-resolution measurements DC magnetic field, strong design heritage from...
Partial detachment is the desired regime for baseline burning plasma scenario in ITER and next-step devices, as it allows to dissipate majority of energy carried by charged particles through scrape-off-layer (SOL) thus avoids localised heat flux deposition divertor region.The COMPASS tokamak equipped with an open has a relatively short connection length, both factors being unfavourable access detachment.As such, only approach naturally detached operation at very high lineaveraged densities...
Power handling experiments with a special liquid metal divertor module based on the capillary porous system technology were performed in tokamak COMPASS. The performance of two metals (Li and LiSn alloy) tested for first time under ELMy H-mode conditions. No damage mesh good exhaust capability observed both separate up to 12 MW/m2 deposited perpendicular, inter-ELM steady-state heat flux ELMs relative energy ~3% local peak fluence at ~15 kJ.m−2. droplets directly ejected from top surface...
Two small liquid metal targets based on the capillary porous structure were exposed to divertor plasma of tokamak COMPASS. The first target was wetted by pure lithium and second one a lithium-tin alloy, both releasing mainly atoms (sputtering evaporation) when plasma. Due poorly conductive material steep surface inclination (implying surface-perpendicular heat flux 12–17 MW/m2) for 0.1–0.2 s, LiSn has reached 900 °C under ELMy H-mode. A model conduction is developed serves evaluate...
This paper presents two scenarios used for generation of a runaway electron (RE) beam in the COMPASS tokamak with focus on decay phase and control beam. The first scenario consists massive gas injection argon into current ramp-up phase, leading to disruption accompanied by plateau generation. In second scenario, smaller amount is order isolate RE from high-temperature plasma. performances radial vertical position feedback were experimentally studied analysed. role energy stability seems be...
Following ELMy H-mode experiments with liquid metal divertor target on the COMPASS tokamak, we predict behavior of a similar Upgrade, where it will be exposed to surface heat fluxes even higher than those expected in future EU DEMO attached divertor.We simulate conduction, sputtering, evaporation, excitation and radiation lithium tin area.Measured high-resolution data from tokamak were rescaled towards Upgrade based many established scalings.Our simulation then yields amount released which...
Abstract The reduction of the incident heat flux onto divertor will be a necessity for future thermonuclear reactors. Impurity seeding is recognized as an efficient way to achieve partial detachment regime, which allows dissipate large fraction power by radiation. This paper presents real-time feedback system (RTFS) based on impurity controlled combined ball-pen and Langmuir probe array in COMPASS tokamak. A number features have been studied, such type impurity, location, constants used...
This contribution presents the experimentally observed edge plasma evolution during limit cycle oscillations (LCO) measured with a new Langmuir and ball-pen multi-pin probe head at COMPASS tokamak. The LCO regime modulates intensity of density fluctuations , radial electric field Er emission frequency 3–5 kHz. grow after decreases in strength which appears to be strongly correlated pressure gradient . magnetic signature shows left–right asymmetry propagation from low high side....
Abstract This work presents the first analysis of disruptive locked mode (LM) triggered by dynamics a confinement change. It shows that, under certain conditions, LM threshold during transient is significantly lower than expected from steady states. We investigate sensitivity to controlled n = 1 error field (EF) activated prior L-H transition in COMPASS tokamak, at q 95 ∼ 3, β N 1, and using EF coils on high-field side vessel. A for penetration subsequent identified, which no significant...
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 COMPASS tokamak is equipped with the soft X-ray (SXR) diagnostic system based on silicon photodiode arrays shielded by a thin beryllium foil. composed of two pinhole cameras having 35 channels each and one vertical camera 20 channels, which was installed recently to improve tomographic inversions. Lines sight SXR detectors cover almost complete poloidal cross section vessel spatial resolution 1-2 cm temporal about 3 μs. Local emissivity reconstructed via Tikhonov regularization...
Abstract Analysis of heat fluxes in scrape-off layer (SOL) plasma is important for the prediction divertor tile loads future reactor-sized tokamak machines. Typically, radial flux profile can be accurately characterized by decay length parameter λ q . The predictions are then based on dependence and machine parameters. In recent years, several empirical scaling models were derived from a collective database lengths observed large tokamaks as well two spherical tokamaks. Most recently, report...
The Neutral Particle Analyzer (NPA) for the COMPASS tokamak was recently upgraded and absolutely calibrated in Ioffe Institute, St. Petersburg.NPA allows simultaneous measurements of energy spectra fast hydrogen deuterium atoms determination ion temperature.Energy neutral fluxes are measured by NPA Ohmic as well NBI heated plasmas.The temperature L-mode plasmas varies range 300-500 eV.After L-H transition, increases ΔT i ≈ 250 eV.A relatively high temporal resolution data acquisition system...
This contribution reviews an important example of current developments in diagnostic systems and data analysis tools aimed at improved understanding control transport processes magnetically confined high temperature plasmas. The choice tungsten for the plasma facing components ITER probably also DEMO means that impurity fusion plasmas is now a crucial challenge. Soft X-ray (SXR) serve as key sensor experimental studies with clear prospective its via actuators based mainly on heating systems....
Runaway electrons, accelerated in a tokamak discharge to high energies (tens of MeV), can cause serious damage plasma facing components. Therefore, it is important develop effective mitigation strategies reduce the risk damage. To study effects various strategies, dedicated diagnostic, calorimetry probe, was developed at COMPASS tokamak. This probe successfully measured heat loads caused by runaway electrons directly, using set temperature sensors embedded graphite body. Deposited energy...
This work presents the first analysis of disruptive locked mode (LM) triggered by dynamics a confinement change. It shows that, under certain conditions, LM threshold during transient is significantly lower than expected from steady states. We investigate sensitivity to controlled $n = 1$ error field (EF) activated prior L-H transition in COMPASS tokamak, at $q_{95} \approx 3$, $\beta_N 1$, and using EF coils on high-field side vessel. A for penetration subsequent identified, which no...