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Qi Xiong

Researcher at Shanghai University

Publications -  7
Citations -  94

Qi Xiong is an academic researcher from Shanghai University. The author has contributed to research in topics: Oxide & Pressurized water reactor. The author has an hindex of 4, co-authored 7 publications receiving 57 citations.

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Characterization of interfacial reactions and oxide films on 316L stainless steel in various simulated PWR primary water environments

TL;DR: In this article, the effect of water chemistry on the electrochemical and oxidizing behaviors of 316L SS was investigated in hydrogenated, deaerated and oxygenated PWR primary water at 310°C.
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Characterization of microstructure of A508III/309L/308L weld and oxide films formed in deaerated high-temperature water

TL;DR: The microstructure of A508III/309L/308L weld clad and the properties of the oxide films formed in simulated pressurized water reactor primary water at 290°C were characterized.
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Magnetoelectropolishing treatment for improving the oxidation resistance of 316L stainless steel in pressurized water reactor primary water

TL;DR: In this paper, the surfaces of 316L stainless steel with mechanical polishing (MP) or electropolishing (EP) in the presence of a magnetic field (MEP) before and after exposure to simulated pressurized water reactor (PWR) primary water were characterized by various techniques such as SEM, Raman spectroscopy, XPS and TEM measurements.
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A magnetic field induced undulated surface and the shift of the active/passivation transition threshold of iron in a sulfuric acid solution

TL;DR: In this article, an unevenly distributed magnetic field caused irreversible electrochemical states of iron in a sulfuric acid solution due to the undulated surface generated by anodic dissolution, and the magnetic field affected the activation-passivation transition threshold by modifying the interface reaction rate and surface morphology.
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Oxidation Resistance and Stress Corrosion Cracking Susceptibility of 308L and 309L Stainless Steel Cladding Layers in Simulated Pressurized Water Reactor Primary Water

TL;DR: In this paper, exposure and slow strain rate tensile tests were conducted in a simulated PWR primary water to investigate the oxidation resistance and stress corrosion cracking (SCC) susceptibility of 308L and 309L stainless steel (SS) cladding layers.