P. Bílková

ORCID: 0000-0002-6156-9773
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About
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Research Areas
  • Magnetic confinement fusion research
  • Fusion materials and technologies
  • Ionosphere and magnetosphere dynamics
  • Superconducting Materials and Applications
  • Laser-Plasma Interactions and Diagnostics
  • Particle accelerators and beam dynamics
  • Plasma Diagnostics and Applications
  • Nuclear reactor physics and engineering
  • Laser-induced spectroscopy and plasma
  • Diamond and Carbon-based Materials Research
  • Fullerene Chemistry and Applications
  • Metal and Thin Film Mechanics
  • Nuclear Physics and Applications
  • GNSS positioning and interference
  • ZnO doping and properties
  • Electronic and Structural Properties of Oxides
  • Electrohydrodynamics and Fluid Dynamics
  • Atomic and Subatomic Physics Research
  • Molecular Junctions and Nanostructures
  • Laser Design and Applications
  • Solar and Space Plasma Dynamics
  • Liquid Crystal Research Advancements
  • Analytical Chemistry and Sensors
  • Electrochemical sensors and biosensors
  • Advancements in Photolithography Techniques

Czech Academy of Sciences, Institute of Plasma Physics
2016-2025

Max Planck Institute for Plasma Physics
2024

Charles University
1997-2021

Czech Academy of Sciences
2005-2021

Culham Science Centre
2013-2021

Czech Technical University in Prague
2017-2021

Royal Military Academy
2020

KTH Royal Institute of Technology
2019

Culham Centre for Fusion Energy
2019

University of York
2019

Abstract In 2021 JET exploited its unique capabilities to operate with T and D–T fuel an ITER-like Be/W wall (JET-ILW). This second major campaign (DTE2), after DTE1 in 1997, represented the culmination of a series enhancements—new fusion diagnostics, new injection capabilities, refurbishment plant, increased auxiliary heating, in-vessel calibration 14 MeV neutron yield monitors—as well as significant advances plasma theory modelling community. DTE2 was complemented by sequence isotope...

10.1088/1741-4326/ad3e16 article EN cc-by Nuclear Fusion 2024-04-12

Abstract The quasi-continuous exhaust (QCE) regime is a that naturally type-I ELM-free. It combines the high density at plasma edge needed for power with normalised energy confinement typical H-mode operation. In QCE large-scale ELMs are avoided and high-frequent, low-amplitude filaments present leading to name-giving transport of particles energy.
This contribution reports first time was successfully achieved in JET metal wall. More so, it demonstrated recent deuterium-tritium...

10.1088/1741-4326/adaa86 article EN cc-by Nuclear Fusion 2025-01-15

The 2014–2016 JET results are reviewed in the light of their significance for optimising ITER research plan active and non-active operation. More than 60 h plasma operation with first wall materials successfully took place since its installation 2011. New multi-machine scaling type I-ELM divertor energy flux density to is supported by principle modelling. relevant disruption experiments modelling reported a set three mitigation valves mimicking setup. Insights L–H power threshold Deuterium...

10.1088/1741-4326/aa5e28 article EN cc-by Nuclear Fusion 2017-06-15

Abstract For the past several years, JET scientific programme (Pamela et al 2007 Fusion Eng. Des . 82 590) has been engaged in a multi-campaign effort, including experiments D, H and T, leading up to 2020 first with 50%/50% D–T mixtures since 1997 ever plasmas ITER mix of plasma-facing component materials. this purpose, concerted physics technology was launched view prepare campaign (DTE2). This paper addresses key elements developed by directly contributing preparation. intense preparation...

10.1088/1741-4326/ab2276 article EN cc-by Nuclear Fusion 2019-05-17

Experimental evidence for the impact of a region high density localised in high-field side scrape-off layer (the HFSHD) on plasma confinement is shown various dedicated experiments ASDEX Upgrade (AUG). Increasing main ion fuelling to increase separatrix and shift profile outwards. Predictive pedestal modelling this indicates 25% decrease attainable top pressure, which compares well with experimental observations gas scan.

10.1088/0741-3335/59/1/014017 article EN Plasma Physics and Controlled Fusion 2016-10-18

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...

10.1088/0741-3335/58/1/014015 article EN cc-by Plasma Physics and Controlled Fusion 2015-10-26

Type I ELMy H-mode operation in JET with the ITER-like Be/W wall (JET-ILW) generally occurs at lower pedestal pressures compared to those full carbon (JET-C). The density is similar but temperature where type ELMs occur reduced and below so-called critical I–type III transition reported JET-C experiments. Furthermore, confinement factor H98(y,2) baseline plasmas JET-ILW low power fractions Ploss/Pthr,08 < 2 (where Ploss (Pin − dW/dt), Pthr,08 L–H threshold from Martin et al 2008 (J. Phys....

10.1088/0029-5515/54/4/043001 article EN Nuclear Fusion 2014-03-10

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 The EUROfusion JET-ILW pedestal database is described, with emphasis on three main issues. First, the technical aspects are introduced, including a description of data selection, datasets, diagnostics used, experimental and theoretical methods implemented definitions. Second, structure stability described. In particular, work describes links between engineering parameters (power, gas divertor configuration) disagreement peeling-ballooning (PB) model ideal magnetohydrodynamics...

10.1088/1741-4326/abb79e article EN Nuclear Fusion 2020-09-11

Within the EUROfusion MST1 work package, a series of experiments has been conducted on AUG and TCV devices to disentangle role plasma fueling shape for onset small ELM regimes. On both devices, regimes with high confinement are achieved if only two conditions fulfilled at same time. Firstly, density separatrix must be large enough (), leading pressure profile flattening separatrix, which stabilizes type-I ELMs. Secondly, magnetic configuration close double null (DN), reduction shear in...

10.1088/1741-4326/ab2211 article EN Nuclear Fusion 2019-05-16

Integrating the plasma core performance with an edge and scrape-off layer (SOL) that leads to tolerable heat particle loads on wall is a major challenge. The new European medium size tokamak task force (EU-MST) coordinates research ASDEX Upgrade (AUG), MAST TCV. This multi-machine approach within EU-MST, covering wide parameter range, instrumental progress in field, as ITER DEMO core/pedestal SOL parameters are not achievable simultaneously present day devices. A two prong adopted. On one...

10.1088/1741-4326/aa6084 article EN cc-by Nuclear Fusion 2017-06-28

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...

10.1088/1741-4326/ab34d2 article EN Nuclear Fusion 2019-07-25

A new system of probes was recently installed in the divertor tokamak COMPASS order to investigate ELM energy density with high spatial and temporal resolution. The consists two arrays rooftop-shaped Langmuir (LPs) used measure floating potential or ion saturation current one array Ball-pen (BPPs) plasma a resolution ~3.5 mm. combination BPPs LPs yields electron temperature microsecond We report on design probe first results profile measurements ELMy H-mode L-mode. also present comparative...

10.1088/1741-4326/aa7e09 article EN Nuclear Fusion 2017-07-06

The self-consistent core-pedestal prediction model of a combination EPED1 type pedestal and simple stiff core transport is able to predict Type I ELMy (edge localized mode) pedestals large JET-ILW (ITER-like wall) database at the similar accuracy as obtained when experimental global plasma β used input. neutral penetration [R. J. Groebner et al., Phys. Plasmas 9, 2134 (2002)] with corrections that take into account variations due gas fueling triangularity density an average error 15%....

10.1063/1.5096870 article EN Physics of Plasmas 2019-07-01

Several series of chlorine‐substituted rod‐like liquid crystalline compounds have been synthesised containing a different number lactate units in the chiral chain. Sequences phases and phase transition temperatures were determined by differential scanning calorimetry, polarising optical microscopy X‐ray diffraction studies. Depending on molecule structure, materials possess rich variety mesophases, i.e. paraelectric smectic A (SmA*), ferroelectric C (SmC*) antiferroelectric (SmCA*) phases....

10.1080/02678290802056212 article EN Liquid Crystals 2008-05-01

Abstract Analysis of the divertor edge localized mode (ELM) electron temperature at a uniquely high temporal resolution (10 −5 s) was reported JET tokamak (Guillemaut et al 2018 Nucl. Fusion 58 066006). By collecting probe data obtained during many dozens ELMs, conditional-average (CAV) technique yields surprisingly low peak temperatures, far below pedestal ones (70%–99% reduction!) which we, however, question. This result interpreted through collisional free-streaming kinetic model by...

10.1088/1741-4326/acbf68 article EN cc-by Nuclear Fusion 2023-02-27

The first-derivative probe technique was applied to derive data for plasma parameters from the IV Langmuir characteristics measured in boundary region COMPASS tokamak and TJ-II stellarator. It is shown that vicinity of last closed flux surface (LCFS) electron energy distribution function (EEDF) bi-Maxwellian with low-temperature fraction predominating over higher temperature one, whereas far scrape-off layer (SOL) EEDF Maxwellian. In stellarator during NBI heated confined close LCFS while...

10.1088/0741-3335/57/11/115011 article EN Plasma Physics and Controlled Fusion 2015-10-06
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