The microstructural evolution was characterized for ZrC ceramics irradiated with 10 MeV Au3+ ions at 800 °C. Post-irradiation examination showed that ZrC did not amorphize at doses up to 30 displacement per atoms (dpa). Concurrent oxidation of ZrC was found to occur during ion irradiation. Coarsening of the defective microstructure, as a function of dose, was revealed by transmission electron microscopy analysis. Black dot defects were observed at low doses (0.5 dpa), and tangled dislocation networks were formed at 5 dpa and above. Diffraction analysis showed a change in the defect structure occurred at doses close to ∼2.5 dpa. The evolution of lattice parameter with dose indicated that uptake of adventitious oxygen could occur in specimens...
© 2020 Elsevier B.V. A Zr3(Al0.9Si0.1)C2 MAX phase-based ceramic with 22 wt.% ZrC and 10 wt.% Zr5Si3...
Zirconium carbide (ZrC) is being considered for utilization in high-temperature gas-cooled reactor f...
International audienceThe development of a new generation of nuclear reactors (Gen-IV), with improve...
A comprehensive understanding of the microstructural evolution of Zirconium Carbide (ZrC2) ceramics ...
Zirconium Carbide (ZrCx ) was irradiated with 10 MeV Au3+ ions to a dose of 10 displacements per ato...
Zirconium carbide is one of the candidate materials to be used for some fuel components of the high ...
Zr2AlC MAX phase-based ceramic material with 33 wt.% ZrC has been irradiated with 22 MeV Au7+ ions b...
International audienceZirconium carbide is one of the candidate materials considered as a component ...
This research revealed the mechanisms of irradiation damage in the novel high entropy ceramic materi...
Recent developments in the synthesis of MAX phases have successfully introduced phases incorporating...
Ceramic materials are useful due to their various properties, making them the material of choice for...
This paper presents the results of a study of changes in structural characteristics, such as the deg...
Expérience GANILInternational audienceCeramics are key engineering materials for electronic, space a...
© 2020 Elsevier B.V. A Zr3(Al0.9Si0.1)C2 MAX phase-based ceramic with 22 wt.% ZrC and 10 wt.% Zr5Si3...
Zirconium carbide (ZrC) is being considered for utilization in high-temperature gas-cooled reactor f...
International audienceThe development of a new generation of nuclear reactors (Gen-IV), with improve...
A comprehensive understanding of the microstructural evolution of Zirconium Carbide (ZrC2) ceramics ...
Zirconium Carbide (ZrCx ) was irradiated with 10 MeV Au3+ ions to a dose of 10 displacements per ato...
Zirconium carbide is one of the candidate materials to be used for some fuel components of the high ...
Zr2AlC MAX phase-based ceramic material with 33 wt.% ZrC has been irradiated with 22 MeV Au7+ ions b...
International audienceZirconium carbide is one of the candidate materials considered as a component ...
This research revealed the mechanisms of irradiation damage in the novel high entropy ceramic materi...
Recent developments in the synthesis of MAX phases have successfully introduced phases incorporating...
Ceramic materials are useful due to their various properties, making them the material of choice for...
This paper presents the results of a study of changes in structural characteristics, such as the deg...
Expérience GANILInternational audienceCeramics are key engineering materials for electronic, space a...
© 2020 Elsevier B.V. A Zr3(Al0.9Si0.1)C2 MAX phase-based ceramic with 22 wt.% ZrC and 10 wt.% Zr5Si3...
Zirconium carbide (ZrC) is being considered for utilization in high-temperature gas-cooled reactor f...
International audienceThe development of a new generation of nuclear reactors (Gen-IV), with improve...