Polycrystalline diamond coating is a promising possibility for prevention, or reduction of high temperature oxidation of zirconium alloys and decrease corrosion rate of zirconium alloy during standard operation. Zirconium alloys are widely used as cladding and construction material in almost all types of nuclear reactors, where usually creates a barrier between nuclear fuel and cooling water in the primary circuit. Hydrogen and considerable amount of heat is released during steam oxidation that may occur in an eventual accident. In this paper zirconium alloy was covered by polycrystalline diamond layer using Plasma Enhanced Linear Antennas Microwave Chemical Vapor Deposition system reactor. X-Ray Diffraction and Raman spectroscopy measurements confirmed coverage of the surface area with crystalline and amorphous carbon layer. Characterizations (Raman spectroscopy) were done for zirconium alloy covered with polycrystalline diamond layer before and after high temperature steam exposure. Weight increase and hydrogen release ware measured during steam exposure.
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2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5005-3
PROCEEDINGS PAPER
High Temperature Oxidation of Polycrystalline Diamond Coated Zirconium Alloy
Jan Škarohlíd,
Jan Škarohlíd
Czech Technical University in Prague, Prague, Czech Republic
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Radek Škoda,
Radek Škoda
Czech Technical University in Prague, Prague, Czech Republic
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Irena Kratochvílová
Irena Kratochvílová
Czech Academy of Science, Prague, Czech Republic
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Jan Škarohlíd
Czech Technical University in Prague, Prague, Czech Republic
Radek Škoda
Czech Technical University in Prague, Prague, Czech Republic
Irena Kratochvílová
Czech Academy of Science, Prague, Czech Republic
Paper No:
ICONE24-60596, V005T15A042; 4 pages
Published Online:
October 25, 2016
Citation
Škarohlíd, J, Škoda, R, & Kratochvílová, I. "High Temperature Oxidation of Polycrystalline Diamond Coated Zirconium Alloy." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 5: Student Paper Competition. Charlotte, North Carolina, USA. June 26–30, 2016. V005T15A042. ASME. https://doi.org/10.1115/ICONE24-60596
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