Highlights • Differences in the evolution of α and βZr microstructures under 6 keV He ion implantation have been analysed as a function of irradiation dose and temperature using in situ TEM. • Both thermal and irradiation stabilities of Zr hydrides particles were studied and were found to dissolve with increasing fluence. • It is suggested that the combination of two different mass-transport mechanisms for He in zircaloy-4 play a major rule in the Zr hydride irradiation-induced dissolution. • He bubble lattices were observed to form during irradiation at 473 K and 1148 K in both crystalline phases, α and βZr, at around the same fluence of 1.7×10^17 ions⋅cm−2 (3.2 dpa)
AbstractZirconium alloys are widely used in nuclear reactors as structural materials. During the ope...
We explore the distribution, morphology and structure of zirconium hydrides formed using different c...
Samples of pure zirconium (Zr) were irradiated by 18 MeV helium (He+) ions in the dose range 0.00162...
Zircaloy-4 alloy specimens consisting of α-Zr grains were irradiated on a tandem accelerator with 5 ...
The authors report here a study of Kr ion implantation and the resultant bubble formation in Zr and ...
Kr ions were used in the HVEM/Tandem facility at ANL to irradiate several Zr alloys, including Zirca...
Ion-beam irradiation has been conducted to demonstrate and assess solid phase dependence of fission ...
Two types of Zr–0.8Sn–1Nb–0.3Fe Zr alloys were irradiated by krypton ions in the t...
The long-term safety of water-based nuclear reactors relies in part on the reliability of zirconium-...
Due to low neutron absorption cross section, high mechanical strength, high thermal conductivity and...
The development of novel materials with future nuclear applications is of ongoing concern.As part of...
The safe and continued operation of the US nuclear power plants requires improvement of the radiatio...
International audienceRecrystallized zirconium alloys are used as nuclear fuel cladding tubes of Pre...
International audienceThe corrosion process (oxidation and hydriding) of the zirconium alloy claddin...
Single crystals of yttria-stabilized zirconia were implanted with 100 keV He ions at two fluences of...
AbstractZirconium alloys are widely used in nuclear reactors as structural materials. During the ope...
We explore the distribution, morphology and structure of zirconium hydrides formed using different c...
Samples of pure zirconium (Zr) were irradiated by 18 MeV helium (He+) ions in the dose range 0.00162...
Zircaloy-4 alloy specimens consisting of α-Zr grains were irradiated on a tandem accelerator with 5 ...
The authors report here a study of Kr ion implantation and the resultant bubble formation in Zr and ...
Kr ions were used in the HVEM/Tandem facility at ANL to irradiate several Zr alloys, including Zirca...
Ion-beam irradiation has been conducted to demonstrate and assess solid phase dependence of fission ...
Two types of Zr–0.8Sn–1Nb–0.3Fe Zr alloys were irradiated by krypton ions in the t...
The long-term safety of water-based nuclear reactors relies in part on the reliability of zirconium-...
Due to low neutron absorption cross section, high mechanical strength, high thermal conductivity and...
The development of novel materials with future nuclear applications is of ongoing concern.As part of...
The safe and continued operation of the US nuclear power plants requires improvement of the radiatio...
International audienceRecrystallized zirconium alloys are used as nuclear fuel cladding tubes of Pre...
International audienceThe corrosion process (oxidation and hydriding) of the zirconium alloy claddin...
Single crystals of yttria-stabilized zirconia were implanted with 100 keV He ions at two fluences of...
AbstractZirconium alloys are widely used in nuclear reactors as structural materials. During the ope...
We explore the distribution, morphology and structure of zirconium hydrides formed using different c...
Samples of pure zirconium (Zr) were irradiated by 18 MeV helium (He+) ions in the dose range 0.00162...