Lukáš Košek

ORCID: 0000-0001-9969-1996
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About
Contact & Profiles
Research Areas
  • Fusion materials and technologies
  • Nuclear Materials and Properties
  • Nuclear reactor physics and engineering
  • Particle accelerators and beam dynamics
  • Thermodynamic and Structural Properties of Metals and Alloys
  • Hydrogen embrittlement and corrosion behaviors in metals
  • nanoparticles nucleation surface interactions
  • Catalytic Processes in Materials Science
  • Advanced Machining and Optimization Techniques
  • Membrane Separation and Gas Transport
  • Nuclear and radioactivity studies
  • Superconducting Materials and Applications
  • Materials Engineering and Processing
  • Cybercrime and Law Enforcement Studies
  • Material Selection and Properties
  • Metal and Thin Film Mechanics
  • Material Properties and Applications
  • Magnetic confinement fusion research
  • Nuclear Engineering Thermal-Hydraulics
  • Metallurgical Processes and Thermodynamics
  • High-Temperature Coating Behaviors
  • Electrodeposition and Electroless Coatings
  • Graphite, nuclear technology, radiation studies
  • Spacecraft and Cryogenic Technologies

University of Chemistry and Technology, Prague
2024

Research Centre Rez
2013-2022

Nuclear Research Institute Rez (Czechia)
2011-2020

Helium is a by-product of the tritium formation reaction by neutron bombardment lithium. The solubility helium estimated to be extremely low, which may result into gas pockets formation. These then cause hot spots within blanket, reduce its shielding properties and also breeding ratio limiting Pb-16Li volume inside blanket. To assess extent bubble formation, simplified model single sector European DEMO blanket had been developed local production rates gaseous have estimated. Based on recent...

10.1016/j.fusengdes.2017.05.100 article EN cc-by-nc-nd Fusion Engineering and Design 2017-06-10

Abstract Heavy liquid metal (HLM) cooled systems are under wide investigation and development. The technology needs to study the materials corrosion, which has a different progress than corrosion caused by aqueous media. Improvement of resistance can be achieved alloying bare material, but degradation steels continues with less or more intensity. Deposition protective barrier may reduce metals dissolution diffusion lead into steel substrate. Different types surface treatment coatings...

10.1115/1.4048631 article EN Journal of Nuclear Engineering and Radiation Science 2020-11-10

Oxygen has a fundamental role for the safe operation of GEN IV reactors cooled by Heavy Liquid Metals, HLM. The use oxygen sensors and dosing gas in environment are key issues chemistry control HLMs, particular when corrosion structural materials is concern. In fact, concentration must be high enough to grow protective oxide scale on surface construction (steels) order prevent their dissolution liquid metal. On other hand, certain threshold not exceeded precipitation oxides within flow paths...

10.1115/icone21-16483 article EN Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications 2013-07-29

Abstract Development of liquid lead cooled nuclear systems requires consideration compatibility issues with the construction materials. In order to understand corrosion or passivation behavior 316 L austenitic stainless steel, steel specimens were exposed for 1000 h in 1 × 10−7 wt % oxygen level at 480 °C static and flowing (velocity 1.6 m/s) conditions. Post-test microscopy investigation using scanning electron microscope focused ion beam (FIB) was performed it demonstrated significant...

10.1115/1.4049719 article EN Journal of Nuclear Engineering and Radiation Science 2021-01-17

Abstract This work deals with behaviour of steel in liquid lead environment and possibilities corrosion resistance improvement. Liquid metal cooled systems are under wide investigation development represent a good alternative. It is necessary to find materials, which would be affected by minimally. Austenitic 316L without coating coated TiSiC was studied flowing lead. Conditions the experiment simulated real system. Deposition protective barrier reduced metals dissolution diffusion into...

10.2478/kom-2020-0017 article EN Koroze a ochrana materialu 2020-12-01
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