Long-Term Oxidation of Zirconium Alloy in Simulated Nuclear Reactor Primary Coolant—Experiments and Modeling
Sign Up to like & getrecommendations! Published in 2023 at "Materials"
DOI: 10.3390/ma16072577
Abstract: Oxidation of Zr-1%Nb fuel cladding alloy in simulated primary coolant of a pressurized water nuclear reactor is followed by in-situ electrochemical impedance spectroscopy. In-depth composition and thickness of the oxide are estimated by ex-situ analytical… read more here.
Keywords: nuclear reactor; oxidation; primary coolant; alloy simulated ... See more keywords
Corrosion Mechanism and Electrochemical Reactions on Alloy 690 in Simulated Primary Coolant of Water–Water Energy Reactors
Sign Up to like & getrecommendations! Published in 2024 at "Materials"
DOI: 10.3390/ma17081846
Abstract: During the power operation of the primary loop of a water cooled–water moderated energy reactor (WWER), the water chemistry evolves from a high-boron high-potassium composition to significantly lower concentrations of both constituents at the end… read more here.
Keywords: chemistry; energy; water; alloy 690 ... See more keywords