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Keywords: zirconium alloy
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Journal Articles

Technical Note: Effect of High-Current Pulsed Electron Beam Processing of Zr-1%Nb Alloy on Its Oxidation Kinetics at 1,200°C in Air and Steam

Mikhail Slobodyan, Konstantin Ivanov, Maxim Elkin, Vasiliy Klimenov, Sergey Pavlov, Gennady Remnev, Irina Strelkova, Vladislav Tarbokov
Journal: Corrosion
CORROSION (2022) 78 (2): 163–167.
https://doi.org/10.5006/3942
Published: 28 December 2021
... cladding made of zirconium alloys under the LOCA conditions in accordance with the nuclear industry standards. Their tasks have been to understand the feasibility of further in-depth research using advanced methods of studying both modified surface and oxide layers, as well as optimizing the HCPEB...
View articletitled, Technical Note: Effect of High-Current Pulsed Electron Beam Processing of Zr-1%Nb Alloy on Its Oxidation Kinetics at 1,200°C in Air and Steam
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Journal Articles

Local Corrosion Behavior of Zr-1Nb Cladding in Water-Water Energetic Reactor Primary Coolants Under Ambient Conditions and at High Temperature

A. Somogyi, A. Horvath, G. Nagy
Journal: Corrosion
CORROSION (2011) 67 (6): 066001-1–066001-6.
https://doi.org/10.5006/1.3600451
Published: 01 June 2011
... acid corrosion critical pitting potential high-temperature electrochemistry localized corrosion pitting pressurized water reactors zirconium alloy The alloy Zr-1Nb (also known as E110) is used as fuel cladding material in Russian-type water-water energetic reactor (VVER) nuclear reactors...
View articletitled, Local Corrosion Behavior of Zr-1Nb Cladding in Water-Water Energetic Reactor Primary Coolants Under Ambient Conditions and at High Temperature
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