Research activities in the Czech Republic focusing on materials and technologies for advanced helium-cooled nuclear reactors

Authors

  • Jan Berka Centum výzkumu Řež s.r.o., Hlavní 130, 250 68 Řež, Czech Republic; University of Chemistry and Technology, Department of Sustainable Fuels and Green Chemistry, Technická 1905, 166 28 Prague, Czech Republic
  • Tereza Válková Centum výzkumu Řež s.r.o., Hlavní 130, 250 68 Řež, Czech Republic; University of Chemistry and Technology, Department of Power Engineering, Technická 1905, 166 28 Prague, Czech Republic https://orcid.org/0009-0009-4682-9563
  • Jan Vít Centum výzkumu Řež s.r.o., Hlavní 130, 250 68 Řež, Czech Republic https://orcid.org/0000-0002-6556-550X
  • Tomáš Melichar Centum výzkumu Řež s.r.o., Hlavní 130, 250 68 Řež, Czech Republic
  • Tomáš Hlinčík University of Chemistry and Technology, Department of Sustainable Fuels and Green Chemistry, Technická 1905, 166 28 Prague, Czech Republic https://orcid.org/0000-0003-4992-9892

DOI:

https://doi.org/10.14311/AP.2025.65.0578

Keywords:

very high-temperature reactor, VHTR, gas-cooled fast reactor, GFR, nuclear structure materials, nuclear technologies, corrosion, gasket, helium, S-Allegro, reactor safety

Abstract

Organisations in the Czech Republic are involved in international research and development of advanced helium-cooled nuclear reactors, including both the very-high-temperature reactors (VHTRs) and the gas-cooled fast reactors (GFRs). To support this effort, a dedicated research infrastructure has been developed and constructed, incorporating large-scale facilities, such as the High-Temperature Helium Loop (HTHL), the S-Allegro helium loop, and other specialised equipment. Current studies are investigating the resistance of structural materials in high-temperature helium environments. Various metallic alloys and ceramic materials intended for high-temperature applications are tested at 750–900 °C. Additional activities focus on helium-coolant technologies – particularly purification, purity monitoring, recovery, and primary-circuit sealing – and on reactor safety and system behaviour under off-normal and emergency conditions.

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References

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Published

2026-01-15

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How to Cite

Berka, J., Válková, T., Vít, J., Melichar, T., & Hlinčík, T. (2026). Research activities in the Czech Republic focusing on materials and technologies for advanced helium-cooled nuclear reactors. Acta Polytechnica, 65(6), 578–588. https://doi.org/10.14311/AP.2025.65.0578