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Polycrystalline Diamond and Cr Double Coatings Protect Zr Nuclear Fuel Tubes Against Accidental Temperature Corrosion in Water-Cooled Nuclear Reactors

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Coatings for High-Temperature Environments

Part of the book series: Engineering Materials ((ENG.MAT.))

Abstract

The chapter proposes a new strategy for protecting Zr alloy nuclear fuel tubes from accidental temperature corrosion in water-cooled nuclear reactors. Protection of the zirconium alloy fuel tubes against accidental temperature corrosion in water-cooled nuclear reactors is important for the safety and efficiency of nuclear power plants, as corrosion in fuel tubes can lead to accidents and reduce the lifespan of the fuel. The new strategy of zirconium alloy fuel tubes from accidental temperature corrosion presented here involves a combination of polycrystalline diamond (PCD) and chromium (Cr) layers. The PCD layer prevents direct interaction between the Zr alloy surface and the hot water environment of the reactor and releases carbon into the underlying Zr material to alter conditions for the penetration of oxygen and hydrogen. The Cr layer helps to reduce corrosion by forming carbides and improving adhesion of the coatings to the Zr alloy substrate. The chapter also discusses the importance of the order of the Cr and PCD layers and the parameters affecting the corrosion of coated ZIRLO tubes. Overall, this new strategy has the potential to significantly improve nuclear safety.

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Authors and Affiliations

  1. Institute of Physics of the Czech Academy of Sciences, Na Slovance 2, 182 21, Prague, Czech Republic

    Irena Kratochvílová, Petr Ashcheulov & Jakub Luštinec

  2. Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, Břehová 78/7, 115 19, Prague, Czech Republic

    Irena Kratochvílová & Jakub Luštinec

  3. Faculty of Environmental Technology, Department of Power Engineering, University of Chemistry and Technology Prague, Technická 1903/3, 166 28, Prague, Czech Republic

    Jan Macák & Petr Sajdl

  4. Robotics and Cybernetics, Czech Technical University in Prague, Czech Institute of Informatics, Jugoslávských partyzánů 1580/3, 160 00, Prague, Czech Republic

    Radek Škoda

Authors
  1. Irena Kratochvílová
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  2. Petr Ashcheulov
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  3. Jakub Luštinec
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  4. Jan Macák
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  5. Petr Sajdl
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Correspondence to Irena Kratochvílová .

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Editors and Affiliations

  1. FunGlass—Centre for Functional and Surface Functionalized Glass, Alexander Dubček University of Trenčín, Trenčín, Slovakia

    Amirhossein Pakseresht

  2. FunGlass—Centre for Functional and Surface Functionalized Glass, Alexander Dubček University of Trenčín, Trenčín, Slovakia

    Kamalan Kirubaharan Amirtharaj Mosas

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Kratochvílová, I., Ashcheulov, P., Luštinec, J., Macák, J., Sajdl, P., Škoda, R. (2024). Polycrystalline Diamond and Cr Double Coatings Protect Zr Nuclear Fuel Tubes Against Accidental Temperature Corrosion in Water-Cooled Nuclear Reactors. In: Pakseresht, A., Amirtharaj Mosas, K.K. (eds) Coatings for High-Temperature Environments. Engineering Materials. Springer, Cham. https://doi.org/10.1007/978-3-031-45534-6_4

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