Abstract

The growth of oxide film, which results from the inward oxygen diffusion from a corrosive environment, is a critical consideration for the corrosion resistance of zirconium alloys. This work calculates the oxygen diffusion coefficients in the oxide films formed on zirconium alloys annealed at 400~500 °C and investigates the related corrosion behavior. The annealed samples have a close size for the second-phase particles but a distinctive hardness, indicating the difference in substrate conditions. The weight gain of all samples highly follows parabolic laws. The weight gain of the sample annealed at 400 °C has the fastest increase rate at the very beginning of the corrosion test, but its oxide film has the slowest growth rate as the corrosion proceeds. By contrast, the sample annealed at 500 °C shows the lowest weight gain but the highest corrosion rate constant. Such a corrosion behavior is attributed to the amount of defects existing in the oxide film formed on the annealed samples; fewer defects would provide a lower fraction of short-circuit diffusion in total diffusion, resulting in a lower diffusion coefficient of oxygen in the oxide film, thereby producing better corrosion resistance. This is consistent with the calculated diffusion coefficients of oxygen in the oxide films: 3.252 × 10−11 cm2/s, 3.464 × 10−11 cm2/s and 3.740 × 10−11 cm2/s for the samples annealed at 400 °C, 450 °C, and 500 °C, respectively.

Highlights

  • Zirconium (Zr) alloys are widely used as fuel claddings in nuclear reactors due to their adequate mechanical properties, low neutron absorption rate, and excellent corrosion resistance in service environments [1,2,3,4]

  • The calculated results illustrate the growth of the oxide film formed on the samples annealed at different temperatures, which advances the understanding of the corrosion behavior of Zr alloys

  • FA-400 has the highest hardness of 241 HV, which is greater than the hardness of FA-450 and FA-500 (233 HV and 222 HV, respectively)

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Summary

Introduction

Zirconium (Zr) alloys are widely used as fuel claddings in nuclear reactors due to their adequate mechanical properties, low neutron absorption rate, and excellent corrosion resistance in service environments [1,2,3,4]. The growth of oxide films formed on Zr alloys is determined by the inward diffusion of the oxidizing medium from the corrosive environments to the metal substrate [6,12,15]. Once the concentration of O in a Zr-rich phase exceeds its solid solubility, an oxide film is formed In this stage, the oxide films are only in a few monoatomic layers (~2 nm in thickness) [17]. Like the growth of oxide films, the corrosion rate of Zr alloy gradually decreases when the oxide films become protective. The calculated results illustrate the growth of the oxide film formed on the samples annealed at different temperatures, which advances the understanding of the corrosion behavior of Zr alloys

Sample
Characterizations
Model and Calculation Method
Schematic
Results and Discussion
Corrosion Kinetics and the Phase Constituents of the Corroded Samples
Weight
Diffusion Coefficient of Oxygen in Oxide Film
Diffusion Coefficient of Oxygen in a Substrate
Oxide Growth of the Low-Temperature Annealed Samples
Conclusions
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