Advanced Coating Materials

0500936 - FZÚ 2019 RIV US eng M - Monography Chapter
Kratochvílová, Irena - Škoda, R. - Taylor, Andrew - Škarohlíd, J. - Ashcheulov, Petr - Fendrych, František
Polycrystalline diamond coating protects Zr cladding surface against corrosion in water-cooled nuclear reactors: Nuclear fuel durability enhancement.
Advanced Coating Materials. Beverly: Wiley-Scrivener, 2018 - (Li, L.; Yang, Q.), s. 123-156. Advanced Material. ISBN 978-1119407560
R&D Projects: GA MŠMT EF16_013/0001406; GA MŠMT(CZ) LO1409; GA MŠMT(CZ) LM2015088
Grant - others:OP VVV - SAFMAT(XE) CZ.02.1.01/0.0/0.0/16_013/0001406
Institutional support: RVO:68378271
Keywords : polycrystalline diamond * Zr cladding * surface oxidation * plasma enhanced chemical vapour
OECD category: Nuclear related engineering

In this chapter we demonstrate a new strategy for the protection of zirconium (Zr) nuclear fuel cladding material by composite polycrystalline diamond (PCD) layers against corrosion in water-cooled nuclear reactors. We show that Zr alloy surfaces can be effectively protected against oxygen and hydrogen uptake at both accident and working temperatures in water-cooled nuclear reactor environments by coating the Zr surface with PCD layers grown in a microwave plasma chemical vapour deposition apparatus. This composition enables PCD layers to have suitable thermal expansion over a wide range of temperatures leading to no delamination. A key requirement is effective protection of Zr alloy surfaces against oxidation and hydration under standard operating conditions (360 °C). Oxidation of PCD-coated Zr alloysurfaces after more than 100 days in 360 °C hot water was significantly decreased (35-55%) compared with that of unprotected Zr alloy processed under the same conditions.

Permanent Link: http://hdl.handle.net/11104/0292975