A new anticorrosion strategy for Zr nuclear fuel claddings will be presented and explained. The dissertation deals with a protection of zirconium (Zr) nuclear fuel cladding material against corrosion in water-cooled nuclear reactors by coating by polycrystalline diamond (PCD) or chromium-aluminum-silicon nitrate (CrAlSiN) layers. It was shown 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 by PCD layer or CrAlSiN each in specific way and for...
