Radek Škoda

ORCID: 0000-0002-8409-2349
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About
Contact & Profiles
Research Areas
  • Nuclear reactor physics and engineering
  • Nuclear Materials and Properties
  • Nuclear and radioactivity studies
  • Nuclear Physics and Applications
  • Graphite, nuclear technology, radiation studies
  • Fusion materials and technologies
  • Nuclear Engineering Thermal-Hydraulics
  • Diamond and Carbon-based Materials Research
  • Integrated Energy Systems Optimization
  • Building Energy and Comfort Optimization
  • Molten salt chemistry and electrochemical processes
  • Geothermal Energy Systems and Applications
  • Magnetic properties of thin films
  • Thermodynamic and Exergetic Analyses of Power and Cooling Systems
  • Advanced Data Storage Technologies
  • Radiation Detection and Scintillator Technologies
  • Metal and Thin Film Mechanics
  • Phase-change materials and chalcogenides
  • Thermodynamic and Structural Properties of Metals and Alloys
  • Radioactive element chemistry and processing
  • Freezing and Crystallization Processes
  • Perovskite Materials and Applications
  • Magnetic Properties and Applications
  • Fluid Dynamics and Heat Transfer
  • Semiconductor materials and devices

Czech Technical University in Prague
2014-2024

University of West Bohemia
2014-2024

Institute of Informatics of the Slovak Academy of Sciences
2019

Texas A&M University
2011-2015

Brno University of Technology
2010

General Electric (United States)
1960-1985

A freeze valve is a unique device for pipe sealing in molten salt applications. The present study focuses on the experimental investigation of operations, with particular interest opening time different variations geometry valve. was based design used Oak Ridge Molten Salt Reactor Experiment. tested valves varied thickness flattened part. An apparatus built to test valves. Good repeatability tests achieved standard deviation less than 5 % time. Results from experiments indicated that...

10.14311/tpfm.2025.019 article EN 2025-01-01

Small modular reactors (SMRs) offer simple, standardized, and safe designs for new nuclear reactor construction. They are factory built, requiring smaller initial capital investment facilitating shorter construction times. SMRs also promise competitive economy when compared with the current fleet. Construction cost of a majority projects, which mostly in their design stages, is not publicly available, but variable costs can be determined from fuel enrichment, average burn-up, plant thermal...

10.4236/epe.2014.65009 article EN cc-by Energy and Power Engineering 2014-01-01

10.1016/j.nima.2008.03.027 article EN Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment 2008-03-24

In this work, we demonstrate and describe an effective method of protecting zirconium fuel cladding against oxygen hydrogen uptake at both accident working temperatures in water-cooled nuclear reactor environments. Zr alloy samples were coated with nanocrystalline diamond (NCD) layers different thicknesses, grown a microwave plasma chemical vapor deposition apparatus. addition to showing that such NCD layer prevents the from directly interacting water, show carbon released film enters...

10.1038/s41598-017-06923-4 article EN cc-by Scientific Reports 2017-07-19

The purpose of this work is to determine the process parameters which control lifetime magneto-optic recording materials and evaluate their useful life in terms fundamental physical domain size. amorphous films were prepared by r.f. bias sputtering, about 100 nm thick, provide an easy axis perpendicular plane film. Their composition was approximately Co <inf xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">80</inf> Gd...

10.1109/tmag.1985.1063925 article EN IEEE Transactions on Magnetics 1985-09-01

10.1016/0001-6160(59)90144-0 article AF Acta Metallurgica 1959-10-01

10.1016/0001-6160(60)90172-3 article FR Acta Metallurgica 1960-11-01

Carbon-free thermally driven district cooling systems (DCS) can effectively mitigate the excessive electricity consumption and carbon emissions associated with sector. This study proposes a DCS that employs nuclear heat as primary energy source. The system comprises three main subsystems: station, transmission, station. A heat-only small modular reactor called Teplator, gas boilers, storage are considered to supply required drive absorption chillers; cold compression chillers supplementary...

10.1155/2023/7880842 article EN cc-by International Journal of Energy Research 2023-08-31

Current designs of both large reactor units and small modular reactors utilize a nuclear fuel with increasing enrichment. This demand for better utilization is challenge handling facilities. The operation higher enriched fuels leads to reduced reserves legislative safety criticality limits spent transport, storage final disposal Design changes in these facilities are restricted due boron content steel aluminum alloys that limited by rolling, extrusion, welding other manufacturing processes....

10.1016/j.net.2023.03.024 article EN cc-by-nc-nd Nuclear Engineering and Technology 2023-03-21

The stability of reverse domains in thin films magnetic materials having high coerciv-ity is investigated. It shown that below a critical diameter are unstable and will collapse. To minimize this minimum domain it necessary to wall energy while maximizing the product magnetization times coercivity, M.H<sub>c</sub>. Since M.H<sub>c</sub> tends be nearly constant near compensation temperature, concluded M-Hcare parameters for assessing use-fulness material density thermomagnetic recording applications.

10.1117/12.936074 article EN Proceedings of SPIE, the International Society for Optical Engineering/Proceedings of SPIE 1983-11-10

Background: Zirconium alloys have very useful properties for nuclear facilities applications having low absorption cross-section of thermal electrons, high ductility, hardness and corrosion resistance. However, there is also a significant disadvantage: it reacts with water steam during this (oxidative) reaction releases hydrogen gas, which partly diffuses into the alloy forming zirconium hydrides. A new strategy surface protection against undesirable oxidation in reactors by polycrystalline...

10.2174/2210315506999160304132946 article EN Recent Patents on Nanotechnology 2016-03-22

If we want to decrease the probability of accidents in nuclear reactors, must control surface corrosion fuel rods. In this work used a diamond coating containing <60% and >40% sp2 "soft" carbon phase protect Zr alloy rods (ZIRLO®) against steam at temperatures from 850 °C 1000 °C. A was grown pulse microwave plasma chemical vapor deposition apparatus made strong barrier hydrogen uptake into ZIRLO® (ZIRLO) under all tested conditions. The also reduced ZIRLO hot (for 60 min) 900 30 min)....

10.3390/ma14216315 article EN Materials 2021-10-22
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