The degradation of zirconium (Zr) fuel cladding alloys as a result of oxidation and the effects of hydrogen is a topic of importance to the nuclear industry. This paper presents the results of NanoSIMS studies into the corrosion behavior of Zircaloy-4 and zirconium-niobium (Zr-Nb) alloys through the use of isotopic spiking with 2H and 18O and with samples that are both irradiated and unirradiated. This paper shows that the unique capabilities of the NanoSIMS allow the study of the distribution of hydrogenic species over large areas with submicron resolution, leading to several conclusions. First, 2H and 18O have different distributions within the oxide layer, with oxygen transport being dominated by penetration through cracks, whereas hydrogen transport is largely diffusive in nature. Second, Zircaloy-4 and Nb-containing alloys show different hydrogen distributions within the oxide layer, and the hydrogen distribution in the Nb-containing alloys is strongly affected by exposure to neutron irradiation. Third, the hydrogen diffusion coefficients for Zircaloy-4, Zr-1 wt% Nb, and Zr-2.5 wt% Nb (both in and out of reactor) have been calculated and agree with previous experimental results. Finally, hydrogen in the α-Zr lattice is localized strongly to random, high misorientation grain boundaries.
Author Information
Jones, Christopher
School of Materials, University of Manchester, Manchester, GB
Li, Kexue
School of Materials, University of Manchester, Manchester, GBDept. of Materials, University of Oxford, Oxford, GB
Liu, Junliang
Dept. of Materials, University of Oxford, Oxford, GB
Aarholt, Thomas
Dept. of Materials, University of Oxford, Oxford, GBDept. of Physics, University of Oslo, Oslo, NO
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