Zircaloy-4 (Zr-1.5%Sn-0.2%Fe-0.1%Cr wt%) was electrochemically charged with deuterium to create deuterides and subsequently analysed with atom probe tomography and scanning transmission electron microscopy to understand zirconium hydride formation and embrittlement. At the interface between the hexagonal close packed (HCP) α-Zr matrix and a face centred cubic (FCC) δ deuteride (ZrD1.5–1.65), a HCP ζ phase deuteride (ZrD0.25–0.5) has been observed. Furthermore, Sn is rejected from the deuterides and segregates to the deuteride/α-Zr reaction front
Atom probe tomography has been used to the study the distribution of hydrogen and deuterium in the o...
Due to their low thermal neutron capture cross-section, zirconium alloys are widely used in the nucl...
Zirconium alloys are commonly used in nuclear fuel rod claddings due to their high ductility, good c...
The long-term safety of water-based nuclear reactors relies in part on the reliability of zirconium-...
Analysis and understanding of the role of hydrogen in metals is a significant challenge for the futu...
Deuteride phases in the zirconium-deuterium system in the temperature range 25–286 °C have been stud...
We explore the distribution, morphology and structure of zirconium hydrides formed using different c...
Hydrogen diffusion through the oxide grown on Zr alloys by aqueous corrosion processes plays a criti...
Microstructure and formation mechanisms of δ-hydrides in rolled and recrystallised fine grain (grain...
Microstructure and crystallography of δ phase hydrides in as-received fine grain and ‘blocky alpha’ ...
Zirconium alloy cladding isolates the nuclear fuel rods from water coolant in a nuclear fission reac...
Zirconium alloys are common fuel claddings in nuclear fission reactors and are susceptible to the ef...
Hydrogen embrittlement in Zr alloy fuel cladding is a primary safety concern for water based nuclear...
Zircaloy-4(Zr-1.5%Sn-0.2%Fe-0.1%Cr wt%)is usedas nuclear fuel cladding materials and hydride embritt...
Due to their low thermal neutron capture cross-section, zirconium alloys are widely used in the nucl...
Atom probe tomography has been used to the study the distribution of hydrogen and deuterium in the o...
Due to their low thermal neutron capture cross-section, zirconium alloys are widely used in the nucl...
Zirconium alloys are commonly used in nuclear fuel rod claddings due to their high ductility, good c...
The long-term safety of water-based nuclear reactors relies in part on the reliability of zirconium-...
Analysis and understanding of the role of hydrogen in metals is a significant challenge for the futu...
Deuteride phases in the zirconium-deuterium system in the temperature range 25–286 °C have been stud...
We explore the distribution, morphology and structure of zirconium hydrides formed using different c...
Hydrogen diffusion through the oxide grown on Zr alloys by aqueous corrosion processes plays a criti...
Microstructure and formation mechanisms of δ-hydrides in rolled and recrystallised fine grain (grain...
Microstructure and crystallography of δ phase hydrides in as-received fine grain and ‘blocky alpha’ ...
Zirconium alloy cladding isolates the nuclear fuel rods from water coolant in a nuclear fission reac...
Zirconium alloys are common fuel claddings in nuclear fission reactors and are susceptible to the ef...
Hydrogen embrittlement in Zr alloy fuel cladding is a primary safety concern for water based nuclear...
Zircaloy-4(Zr-1.5%Sn-0.2%Fe-0.1%Cr wt%)is usedas nuclear fuel cladding materials and hydride embritt...
Due to their low thermal neutron capture cross-section, zirconium alloys are widely used in the nucl...
Atom probe tomography has been used to the study the distribution of hydrogen and deuterium in the o...
Due to their low thermal neutron capture cross-section, zirconium alloys are widely used in the nucl...
Zirconium alloys are commonly used in nuclear fuel rod claddings due to their high ductility, good c...