A5017468897- Magnetic confinement fusion research
- Fusion materials and technologies
- Nuclear reactor physics and engineering
- Magnetic Field Sensors Techniques
- Superconducting Materials and Applications
- Advanced Thermodynamic Systems and Engines
- Nuclear Materials and Properties
- Heat transfer and supercritical fluids
- Atomic and Subatomic Physics Research
- Nuclear Physics and Applications
- Particle accelerators and beam dynamics
- Refrigeration and Air Conditioning Technologies
- Physics of Superconductivity and Magnetism
- Non-Destructive Testing Techniques
- Ionosphere and magnetosphere dynamics
- Thermodynamic and Exergetic Analyses of Power and Cooling Systems
- Network Traffic and Congestion Control
- Heat and Mass Transfer in Porous Media
- Nuclear Engineering Thermal-Hydraulics
- Mobile Agent-Based Network Management
- Distributed systems and fault tolerance
- Spacecraft and Cryogenic Technologies
- Laser-Plasma Interactions and Diagnostics
- Transportation Safety and Impact Analysis
- Engineering Structural Analysis Methods
Czech Academy of Sciences, Institute of Plasma Physics
2015-2024
Czech Technical University in Prague
2015-2024
University of Chemistry and Technology, Prague
2023
Moscow Engineering Physics Institute
2020
Czech Academy of Sciences
2019
Research Centre Rez
2014-2015
The plasma diagnostic and control (D&C) system for a future tokamak demonstration fusion reactor (DEMO) will have to provide reliable operation near technical physics limits, while its front-end components be subject strong adverse effects within the nuclear high temperature environment. ongoing developments ITER D&C represent an important starting point progressing towards DEMO. Requirements detailed exploration of are however pushing design using sophisticated methods aiming large spatial...
Conceptual design activities of the first fusion power plants were launched in recent years with a view to putting them into operation by 2050. Nuclear offers significant benefits comparison exploited energy sources, especially limitless fuel reserves, inherent nuclear safety, and negligible impact on environment. The challenge is high heat neutron loading reactors zone. paper brings ex-ante economic analysis plant model DEMO2 terms cost electricity. investment operating costs are presented....
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,...
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...
Performance of bismuth Hall sensors developed for the ITER steady state magnetic diagnostic was investigated high fields in range ±7 T. Response to field found be nonlinear particularly within ±1 Significant contribution planar effect output voltage causing undesirable cross sensitivity identified. It demonstrated that this can minimized by optimization sensor geometry and alignment with application "current-spinning technique."
The measurements of the magnetic field in tokamaks such as ITER and DEMO will be challenging due to long pulse duration, high neutron flux, elevated temperatures. duration plasma makes standard techniques, inductive coils, prone errors. At same time, hostile environment, with repairs possible only on blanket exchange, if at all, requires a robust sensor. This contribution presents final design novel, steady-state, sensors for ITER. A poloidal array 60 mounted vacuum vessel outer shell...
Ceramic-chromium Hall sensors represent a temperature and radiation resistant alternative to based on semiconductors. Demand for these is presently motivated by the ITER DEMO nuclear fusion projects. The developed ceramic-chromium were tested up of 550 °C magnetic field 14 T. magnitude sensitivity sensor was 6.2 mV/A/T at 20 4.6 500 °C. observed be weakly dependent above 240 with an average coefficient 0.014%/°C independent relative deviation below measurement accuracy 0.086%. A simulation...
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...
The transition to low-carbon technologies lies in the support of modern energy sources, which are also represented by fusion power plants. One first plants will be European Union DEMOnstration plant. Among key attributes that influence entire design this plant, belongs conversion system. In addition classic Rankine steam cycle, it is possible use different cooling media, such as supercritical CO2 Brayton cycle. advantages mainly compactness system, is, lower investment costs for plant while...
DEMO fusion power reactor features multiple different grade heat sources, like the first wall and blanket, divertor, vacuum vessel. The way of using these sources their compatibility with conversion cycle will affect efficiency electricity production. A significant complication is a pulse operation unless noninductive generation plasma electric current developed. In this case, an energy storage application necessary for conventional This article focused on supercritical CO <sub...
A recent improvement of the design ITER outer vessel steady-state magnetic field sensors (OVSS) is presented. OVSS features a pair Hall with sensing layer made bismuth. Sixty will be installed on vacuum skin to perform an absolute measurement field. The bismuth sensor temperature dependent, and maximum allowed error 4-mT limits by on-board thermocouple less than 0.28 °C. This consists difference between sensors, calibration error, error. improved housing reduces bellow 0.04 Procedures prior...
The water-cooled WCLL blanket is one of the possible candidates for fusion power reactors. plasma-facing first wall manufactured from reduced-activation ferritic-martensitic steel Eurofer97 will be cooled with water at a typical pressurized reactor (PWR) conditions. According to new estimates, exposed peak heat fluxes up 7 MW/m2 while maximum operated temperature set 550 °C. performed analysis shows capability designed flat concept remove flux without exceeding operating only 0.75 MW/m2....