Influence of water chemistry on the corrosion mechanism of a zirconium–niobium alloy in simulated light water reactor coolant conditions

Bojinov, Martin; Karastoyanov, Vasil; Kinnunen, Petri; Saario, Timo

doi:10.1016/j.corsci.2009.08.045

Cited by 78 publications

(32 citation statements)

References 45 publications

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“…As for Zr R60702, Zr is an active metal that tends to absorb oxygen, hydrogen, and some other light elements, especially when the temperature is over 200 °C, it can capture a large amount of oxygen. Zr oxide is prone to generate when the amount of oxygen concentration is over 0.3% . During welding, Zr oxide will inevitably appear as there is a slight amount of oxygen in the filler wires and the inadequate protection of argon, leading to the electrochemical inhomogeneity between grains and grain boundaries.…”

Section: Resultsmentioning

confidence: 99%

Corrosion behavior of Zirconium R60702 weldment in 75 wt% sulfuric acid

Yao

Luo

Wei

et al. 2013

Materials and Corrosion

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Zirconium R60702 weldment was achieved by tungsten inert gas welding. Hot acid corrosion and electrochemical corrosion tests were performed on the specimens taken from the base metal (BM), the heat-affected zone (HAZ), and the weld zone (WZ) of the weldment in 75 wt% sulfuric acid. Metallographic examination and X-ray diffraction (XRD) analysis showed that the impurity generating in the weldment during welding was zirconium dioxide. Cumulative mass loss test demonstrated that the BM exhibited good resistance to hot acid corrosion, the HAZ less, and the WZ least. Scanning electron microscope images illustrated that the corrosion mechanism of the BM was pitting whereas that of the WZ was inter-granular corrosion. In contrast, pitting and inter-granular coexisted in the HAZ. Anodic polarization and electrochemical impedance spectroscopy tests showed similar result to that of the hot acid corrosion test. In the electrochemical corrosion condition, the WZ had worse corrosion resistance than the other two parts. Therefore, the WZ is the key area of corrosionresistance protection of the Zr R60702 weldment.

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Section: Resultsmentioning

confidence: 99%

Corrosion behavior of Zirconium R60702 weldment in 75 wt% sulfuric acid

Yao

Luo

Wei

et al. 2013

Materials and Corrosion

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“…However, the Fukushima accident demonstrates the importance of understanding the oxidation behavior of zirconium alloys, as they shield the radioactive materials (i.e., uranium, fission gas) and the degradation of the zirconium cladding directly contributes to severe accidents in nuclear power plants. Furthermore, zirconium oxide forms at the water-metal interface, and its structure and phase determine its mechanical properties [1][2][3][4][5][6][7][8][9][10][11][12][13][14][15][16][17][18]. Therefore, to ensure the safety of the nuclear power reactors, the corrosion mechanism and sustainability of the zirconium based alloy materials must be understood.…”

Section: Introductionmentioning

confidence: 99%

Phase transformation of oxide film in zirconium alloy in high temperature hydrogenated water

Kim

Choi

et al. 2015

Corrosion Science

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“…Potentiodynamic polarization tests were carried out using a Bio-Logic SP-150 potentiostat/galvanostat for uncoated, PEO-coated and inside surface of black oxide samples at room temperature (20 ºC) in a 4.8 wt.% (0.2mol/L or 1400ppm Li + ) LiOH solution, which is very corrosive to Zr alloys [14,15]. The exposure area of the samples was 1 cm2.…”

Section: Methodsmentioning

confidence: 99%

Plasma Electrolytic Oxidation (PEO) coatings on a zirconium alloy for improved wear and corrosion resistance

Chen

Nie

Northwood

2010

Tribology and Design

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Zr oxide coatings were deposited using plasma electrolytic oxidation (PEO) on Zr-2.5wt%Nb (Zr-2.5Nb) alloy, which is currently used for pressure tubes in the CANDU nuclear reactor. The effects of two PEO processing factors, electrolyte concentration and current density, on the microstructure and properties of the coatings were systematically investigated. The coating morphology and chemical composition were determined using scanning electron microscopy (SEM) and energy dispersive X-ray analysis (EDX). Potentiodynamic polarization corrosion testing was used to examine the corrosion resistance of the coatings in a dilute aqueous, LiOH solution. Pin-on-disc wear tests were performed under dry and lubricated sliding conditions. SEM was also used to characterize the wear traces on the coated and uncoated surfaces. A 30-day autoclave experiment was carried out to study the corrosion performance of the Zr-2.5Nb substrate, PEO coatings and a commercial autoclaved black oxide coating. Based on the results of this research, recommendations are made as to processing parameters for the production of oxide coatings with improved wear and corrosion resistance.

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Influence of water chemistry on the corrosion mechanism of a zirconium–niobium alloy in simulated light water reactor coolant conditions

Cited by 78 publications

References 45 publications

Corrosion behavior of Zirconium R60702 weldment in 75 wt% sulfuric acid

Corrosion behavior of Zirconium R60702 weldment in 75 wt% sulfuric acid

Phase transformation of oxide film in zirconium alloy in high temperature hydrogenated water

Plasma Electrolytic Oxidation (PEO) coatings on a zirconium alloy for improved wear and corrosion resistance

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