M. Farník

ORCID: 0000-0002-9100-7093
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About
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Research Areas
  • Magnetic confinement fusion research
  • Particle accelerators and beam dynamics
  • Fusion materials and technologies
  • Plasma Diagnostics and Applications
  • Superconducting Materials and Applications
  • Ionosphere and magnetosphere dynamics
  • Nuclear Physics and Applications
  • Atomic and Subatomic Physics Research
  • Laser-Plasma Interactions and Diagnostics
  • Nuclear reactor physics and engineering
  • Semiconductor materials and devices
  • Electron and X-Ray Spectroscopy Techniques
  • Particle Detector Development and Performance
  • Spacecraft and Cryogenic Technologies
  • Radiation Detection and Scintillator Technologies
  • Gyrotron and Vacuum Electronics Research
  • Quantum and electron transport phenomena
  • Particle Accelerators and Free-Electron Lasers
  • Catalytic Processes in Materials Science

Czech Academy of Sciences, Institute of Plasma Physics
2018-2025

Czech Technical University in Prague
2018-2024

Max Planck Institute for Plasma Physics
2024

Czech Academy of Sciences
2021

National Centre for Nuclear Research
2021

Abstract The tokamak à configuration variable (TCV) continues to leverage its unique shaping capabilities, flexible heating systems and modern control system address critical issues in preparation for ITER a fusion power plant. For the 2019–20 campaign configurational flexibility has been enhanced with installation of removable divertor gas baffles, diagnostic capabilities an extensive set upgrades new dual frequency gyrotrons. baffles reduce coupling between main chamber allow detailed...

10.1088/1741-4326/ac369b article EN cc-by Nuclear Fusion 2022-03-01

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,...

10.1016/j.fusengdes.2021.112490 article EN cc-by-nc-nd Fusion Engineering and Design 2021-03-23

Abstract Experiments on ASDEX Upgrade (AUG) in 2021 and 2022 have addressed a number of critical issues for ITER EU DEMO. A major objective the AUG programme is to shed light underlying physics confinement, stability, plasma exhaust order allow reliable extrapolation results obtained present day machines these reactor-grade devices. Concerning pedestal physics, mitigation edge localised modes (ELMs) using resonant magnetic perturbations (RMPs) was found be consistent with reduction linear...

10.1088/1741-4326/ad249d article EN cc-by Nuclear Fusion 2024-01-31

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...

10.1088/1361-6587/aae04a article EN Plasma Physics and Controlled Fusion 2018-09-11

Abstract To achieve their goals, future thermonuclear reactors such as ITER and DEMO are expected to operate plasmas with a high magnetic field, triangularity confinement. address the corresponding challenges, concept of high-field ( <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msub> <mml:mi>B</mml:mi> <mml:mtext>T</mml:mtext> </mml:mrow> </mml:msub> <mml:mtext>⩽</mml:mtext> </mml:math> 5 T), high-current <mml:mi>I</mml:mi>...

10.1088/1741-4326/ad4569 article EN cc-by Nuclear Fusion 2024-04-30

Abstract An overview of recent results obtained at the tokamak ASDEX Upgrade (AUG) is given. A work flow for predictive profile modelling AUG discharges was established which able to reproduce experimental H-mode plasma profiles based on engineering parameters only. In center, theoretical predictions current redistribution by a dynamo effect were confirmed experimentally. For core transport, stabilizing fast ion distributions turbulent transport shown be important explain isotope and...

10.1088/1741-4326/ac207f article EN cc-by Nuclear Fusion 2021-08-24

Abstract Electron cyclotron resonance heating is one of the additional systems that going to be installed at future high-field tokamak COMPASS Upgrade in Prague. Experimental scenarios cover a wide range operational parameters, thus designed system has exceptionally versatile. The simulations wave propagation plasma have been performed using TORBEAM code. obtained results yield important information about density limitations and other constraints ECRH Upgrade, which are necessary for...

10.1088/1361-6587/adaa15 article EN cc-by Plasma Physics and Controlled Fusion 2025-01-14

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...

10.1088/1741-4326/ac301f article EN cc-by Nuclear Fusion 2021-10-17

Due to an increased interest in runaway electron (RE) phenomena tokamak research, the need for diagnostics of population plasma has emerged. A novel diagnostic nonthermal cyclotron emission from electrons can be utilized this purpose. It was designed and installed at COMPASS based on available heterodyne radiometer. The vertical ECE (V-ECE) system uses a 16-channel radiometer with vertically placed E2-band horn antenna 76.5–90 GHz frequency range front-end. Simulations ray-tracing SPECE code...

10.1063/1.5099463 article EN Review of Scientific Instruments 2019-11-01

Abstract The beams of fast runaway electrons (RE), which are often produced during tokamak discharges, particularly dangerous and can induce serious damages the vacuum vessel internal components machine. proper diagnostics RE is essential for controlling discharge, e.g., by early mitigation disruptions potentially beams. usually based on measurements radiation emitted either these electrons, or as a result their interactions with plasma and/or walls. Such recorded means probes placed outside...

10.1140/epjp/s13360-021-01844-8 article EN cc-by The European Physical Journal Plus 2021-10-01

An application study of modern pixel semiconductor detectors for characterization runaway electron events in tokamaks is presented. Characterization techniques utilizing both spectroscopic measurements and monitoring the intensity secondary X-rays produced by electrons were used. Energy spectra time evolutions their on two (Golem Compass) measured under different conditions compared with results standard diagnostics. The energy have similar exponential shapes but a significant variation...

10.1109/nssmic.2018.8824534 article EN 2018-11-01

An electron cyclotron emission (ECE) diagnostic of suprathermal electrons was utilised for runaway (RE) experiments purposes in the COMPASS tokamak. Our vertical ECE (V-ECE) system consists a 16-channel heterodyne radiometer and an E-band horn antenna with 76.5-88 GHz frequency range front-end. Simulations used design showed possibility detecting low-energy (50-140 keV) electrons. We realized measurements both extraordinary (X-) ordinary (O-) mode linear polarizations. The amplitudes X-mode...

10.1051/epjconf/201920303006 article EN cc-by EPJ Web of Conferences 2019-01-01
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