Search Results - Zuyok, V.
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Dispersion fuel for nuclear research facilities by Kushtym, А.V., Belash, M.M., Zigunov, V.V., Slabospitska, O.O., Zuyok, V.A.
Published in Вопросы атомной науки и техники (2017)Get full text
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Assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding by Zuyok, V., Rud, R., Tretyakov, M., Rud, N., Kushtym, Y., Dykyy, I., Shevchenko, I., Rostova, H., Shtefan, V.
Published in Вопросы атомной науки и техники (2022)Get full text
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Protective vacuum-arc coatings on zirconium alloy fuel cladding to prevent catastrophic accidents at nuclear reactors by Kuprin, A.S., Zuyok, V.A., Belous, V.A., Ovcharenko, V.D., Reshetnyak, E.N., Vasilenko, R.L., Tolmachova, G.N., Kushtym, Ya.O.
Published in Problems of Atomic Science and Technology (2023)Get full text
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