Search Results - "Kushtym, Ya. O."

Corrosion Properties Characterization of 06Cr18Ni10Ti, 08Cr18Ni10Ti Steels and 42CrNiMo Alloy under Conditions Simulating Primary Coolant of Pressurized Water Reactor by Zuyok, V. A., Rud, R. A., Tretyakov, M. V., Rud, N. V., Kushtym, Ya. O., Shtefan, V. V.

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Corrosion Resistance of Traditional and Advanced Fuel Rod Cladding Materials for Water-Cooled Reactors by V.A. Zuyok, Yu.V. Kovalenko, V.V. Shtefan, R.O. Rud, M.V. Tretiakov, and Ya.O. Kushtym

“…The available literature experimental data on corrosion resistance of traditional and advanced fuel rod cladding materials for water-cooled reactors are…”
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