Nickel-chromium (Ni–Cr) coatings deposited by magnetron sputtering for accident tolerant nuclear fuel claddings; Surface and Coatings Technology; Vol. 369

Nickel-chromium (Ni–Cr) coatings deposited by magnetron sputtering for accident tolerant nuclear fuel claddings; Surface and Coatings Technology; Vol. 369

Sonraí bibleagrafaíochta
Parent link:Surface and Coatings Technology
Vol. 369.— 2019.— [P. 69-78]
Údair chorparáideacha: Национальный исследовательский Томский политехнический университет Инженерная школа ядерных технологий Отделение экспериментальной физики, Национальный исследовательский Томский политехнический университет Инженерная школа ядерных технологий Научно-образовательный центр Б. П. Вейнберга
Rannpháirtithe: Sidelev D. V. Dmitry Vladimirovich, Kashkarov E. B. Egor Borisovich, Syrtanov M. S. Maksim Sergeevich, Krivobokov V. P. Valery Pavlovich
Achoimre:Title screen
Nickel-chromium coatings were deposited on Zr1Nb alloy using magnetron sputtering systems with «hot» Ni and cooled Cr targets. The effect of coating composition on high-temperature oxidation resistance and hydrogen uptake of Zr1Nb was studied. Hydrogen uptake of the alloy was measured in situ under gas-phase hydrogenation at 633?K. High-temperature oxidation was performed in air atmosphere at 1173–1373?K for 20?min. It was shown that the coating with high Ni content (83?at.%) drastically increases hydrogen uptake of the Zr1Nb alloy and demonstrates low oxidation resistance even at 1173?K. The coatings with Cr content =45?at.% have low hydrogen permeability which reduces the rate of hydrogen uptake of the alloy. The oxidation resistance of the NiCr coatings increases with Cr content in the as-deposited coatings. The pure Cr coating exhibits the best oxidation resistance: only 8?µm-thick oxide layer was observed. There is also found the intensive diffusion of nickel into the alloy during high-temperature oxidation of the samples coated by NiCr films with 55 and 17?at.% Ni. The as-deposited NiCr coatings are less brittle than the pure Cr coating, but their mechanical properties degrade stronger than for the Cr coating after the oxidation test.
Режим доступа: по договору с организацией-держателем ресурса
Teanga:Béarla
Foilsithe / Cruthaithe: 2019
Ábhair:
электронный ресурс
труды учёных ТПУ
nickel-chromium coatings
chromium
nuclear fuel cladding
zirconium alloy
high-temperature oxidation
hydrogen uptake
никельхромовые сплавы
хром
ядерное топливо
циркониевые сплавы
высокотемпературное окисление
Rochtain ar líne:https://doi.org/10.1016/j.surfcoat.2019.04.057
Formáid: Leictreonach Caibidil leabhair
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=660601

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