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Information × Registration Number 0219U100808, 0116U005091 , R & D reports Title Creation barrier protective layers on zirconium fuel claddings by ion-plasma methods, investigation and optimization of their characteristics in order to increase service life and preventing a catastrophic rising of accidents on present and future reactors popup.stage_title Head Bilous Vitalii A., Доктор технічних наук Registration Date 21-03-2019 Organization National Science Center "Kharkiv Institute of Physics and Technology" popup.description2  Optimization of technological processes of deposition of various condensates and formed the following coatingss: TiAlN, TiAlYN, TiAlSiN, TiAlCrYN, Cr/TiAlCrY, Cr/H18N10T, Cr on the samples of the Zr-1Nb alloy. Researched their composition, architecture, structure and physical and mechanical properties. All coatings have a high hardness and oxidize in air at a temperature of 1100 °C within a 1 hour to a depth of no more than 3 microns without changing the structure. Thermal cyclic testing at temperature 600-900 °C of the pressure gas filled layouts fuel elements with coatings show high protective ability of coatings from corrosion of zirconium alloys in such conditions. Developed chromium-based coatings and its nitride can most effectively protect against corrosion of zirconium alloy cladding as in the context of the normal operations of the reactor, and in case of a possible accident with the loss of coolant. Annealing the samples in a vacuum at a temperature exposure does not lead to changes in the structure of chrome coatings, which testifies to their thermal stability at temperatures up to 400 °C. Irradiation of chromium coating with microcrystalline structure by argon ions at a dose of 25 dpa leads to radiation- stimulated isotropic growth of grain size from the original 250 nm to 295 nm and radiation-induced swelling, which begin with a low dose (5 dpa) and reaches the value 0.66%. Therefore, chromium vacuum-arc coatings have high resistance in conditions that simulate operation and accident, and can be applied to protect claddings from oxidation in the nuclear reactor with the aim to prevent nuclear accidents with severe consequences. Product Description popup.authors popup.nrat_date 2020-04-02 Close