AbstractHydrogen content and distribution in Zircaloy-4 cladding samples with controlled hydrogen concentrations up to 1100ppm were studied using neutron radiography and computed tomography. Hydrogen charging was performed in a process tube that was heated to facilitate hydrogen absorption by the metal. A correlation between the hydrogen concentration in the hydrided tubes and the neutron intensity was established, by which hydrogen content can be determined precisely in a small area (55μm × 55 μm). Image analysis was also performed to evaluate the heating rate and its correlation with the hydrogen distribution through hydrided materials. In addition to image analysis, tomography experiments were performed on Zircaloy-4 tube samples to stud...
Analysis and understanding of the role of hydrogen in metals is a significant challenge for the futu...
Under hypothetical loss-of-coolant accident conditions, fuel cladding tubes made of zirconium alloys...
Hydrogen uptake by nuclear fuel claddings during normal operation as well as loss of coolant during ...
AbstractHydrogen content and distribution in Zircaloy-4 cladding samples with controlled hydrogen co...
The presence of hydrogen (H) and zirconium hydrides (ZrH1.7) in Zircaloy-4 nuclear fuel cladding has...
The hydrogen concentration and distribution at both sides of the burst opening of cladding tubes use...
AbstractIn the framework of the post-test examinations of the large-scale LOCA simulation tests at t...
AbstractThe hydrogen concentration and distribution at both sides of the burst opening of cladding t...
Zr-based alloys are used in nuclear power plants because of a unique combination of very low neutron...
In situ neutron radiography experiments can provide information about diffusive processes and the ki...
Hydride precipitation and distribution in hot-rolled and annealed Zircaloy-4 plate samples artificia...
Zircaloy-4, which is widely used as a core structural material in Pressurized-Water Reactors (PWR), ...
International audienceThis study is focused on the hydrogen-induced dimensional change or "growth" o...
The absorption of hydrogen in zirconium-based nuclear fuel cladding alloys is one of the most signif...
A hydrogen container based on the use of a hydride forming material (LaNi5) has been specifically de...
Analysis and understanding of the role of hydrogen in metals is a significant challenge for the futu...
Under hypothetical loss-of-coolant accident conditions, fuel cladding tubes made of zirconium alloys...
Hydrogen uptake by nuclear fuel claddings during normal operation as well as loss of coolant during ...
AbstractHydrogen content and distribution in Zircaloy-4 cladding samples with controlled hydrogen co...
The presence of hydrogen (H) and zirconium hydrides (ZrH1.7) in Zircaloy-4 nuclear fuel cladding has...
The hydrogen concentration and distribution at both sides of the burst opening of cladding tubes use...
AbstractIn the framework of the post-test examinations of the large-scale LOCA simulation tests at t...
AbstractThe hydrogen concentration and distribution at both sides of the burst opening of cladding t...
Zr-based alloys are used in nuclear power plants because of a unique combination of very low neutron...
In situ neutron radiography experiments can provide information about diffusive processes and the ki...
Hydride precipitation and distribution in hot-rolled and annealed Zircaloy-4 plate samples artificia...
Zircaloy-4, which is widely used as a core structural material in Pressurized-Water Reactors (PWR), ...
International audienceThis study is focused on the hydrogen-induced dimensional change or "growth" o...
The absorption of hydrogen in zirconium-based nuclear fuel cladding alloys is one of the most signif...
A hydrogen container based on the use of a hydride forming material (LaNi5) has been specifically de...
Analysis and understanding of the role of hydrogen in metals is a significant challenge for the futu...
Under hypothetical loss-of-coolant accident conditions, fuel cladding tubes made of zirconium alloys...
Hydrogen uptake by nuclear fuel claddings during normal operation as well as loss of coolant during ...