The effect of varying nickel concentration on the hydrogen pickup fraction and corrosion resistance in Zircaloy-4
Source abstract
Abstract
Zircaloy-4 samples with various levels of Ni content (0–483 wt. ppm) were exposed in autoclave for up to 2800 days. Samples were destructively and non-destructively measured to determine the weight gain from oxidation and hydrogen contents to better understand the role hydrogen has in increasing oxide growth rates and to study the effect of Ni on the mechanism of hydrogen pickup in Zr alloys. Overall, additions of Ni lead to significantly higher hydrogen pickup of the alloy. As observed previously, at higher weight gains, a small decrease in hydrogen pickup fraction is observed for all alloys tested (Zircaloy-4 with and without Ni). A small beneficial effect of Ni was observed on corrosion rate when controlling for the amount of hydrogen in the material, which potentially indicates that if hydrogen content were controlled via other means (e.g., volume or other alloy additions) Ni may improve corrosion resistance of the material. Results generally support published density functional theory (DFT) hypotheses that point to an increase in hydrogen solubility or catalysis of surface reactions as the mechanism by which Ni increases hydrogen pickup. Data or future corrosion testing of alloys with Ta, V, or Ti additions could further support or refute these theories by testing aspects of the proposed mechanisms.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (22)
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1. Zirconium alloys in nuclear applications
2. The development of the Zircaloys
3. Hydride formation in zirconum alloys
4. Hydrogen pickup and redistribution in alpha-annealed Zircaloy-4
5. Hydrogen pickup measurements in zirconium alloys: relation to oxidation kinetics10.1016/j.jnucmat.2014.03.001 ↗
6. Effect of alloying elements on hydrogen pickup in zirconium alloys
7. Optimization of Zry-2 for high burnups
8. Microbeam X-Ray absorption near-edge spectroscopy of alloying elements in the oxide layers of irradiated Zircaloy-2
9. Hydrogen absorption by nickel enriched Zircaloy-210.1016/0022-3115(59)90023-6 ↗
10. Impact of additives on zirconium oxidation by water: mechanistic insights from first principles10.1039/c3ra42941e ↗
11. Doping in the valley of hydrogen solubility: a route to designing hydrogen-resistant Zirconium alloys10.1103/PhysRevApplied.5.014008 ↗
12. The role of hydrogen in zirconium alloy corrosion10.1016/j.jnucmat.2017.08.046 ↗
13. Neutron irradiation effects on the corrosion of Zircaloy-4 in a pressurized water reactor environment
14. The influence of in-situ clad straining on the corrosion of Zircaloy in a PWR water environment
15. Microstructural and microchemical analyses of extracted second-phase precipitates in alpha-annealed and beta-quenched Zircaloy-410.1017/S143192761400422X ↗
16. Microbeam synchrotron radiation diffraction and fluorescence of oxide layers formed on zirconium alloys at different corrosion temperatures10.1016/j.jnucmat.2019.151779 ↗
17. Generalized Kearns texture factors and orientation texture measurement10.1016/j.jnucmat.2010.11.031 ↗
18. Corrosion of zirconium alloys used for nuclear fuel cladding10.1146/annurev-matsci-070214-020951 ↗
19. The effect of hydrogen on the transition behavior of the corrosion rate of zirconium alloys
20. Long term corrosion and deuterium uptake in CANDU-PHW pressure tubes
21. Effects of thermomechanical processing on in-reactor corrosion and post-irradiation mechanical properties of Zircaloy-2
22. The effect of minor alloying elements on oxidation and hydrogen pickup in Zr-2.5Nb