Topic
Zirconium alloy
About: Zirconium alloy is a research topic. Over the lifetime, 6548 publications have been published within this topic receiving 78954 citations. The topic is also known as: zircaloy.
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TL;DR: In this paper, a polycrystalline diamond layer was used for protection of zirconium alloy nuclear fuel cladding against undesirable oxidation with no loss of chemical stability and preservation of its functionality.
30 citations
TL;DR: In this paper, the authors performed synchrotron X-ray transmission diffraction experiments to study hydride precipitation and dissolution in the zirconium/zirconia-hydride system while it occurs.
30 citations
TL;DR: In this article, the influence of hydrogen on the performance of zirconium fuel assemblies (FA) was investigated under different conditions of in-pile operation, such as residual manufacturing and operating and absorbed hydrogen.
30 citations
TL;DR: In this paper, a Ti2AlC MAX phase material was deposited on Zircaloy-4 substrate using the cold spray process, with the goal of enhancing the accident tolerance of zirconium-alloy fuel cladding in light water reactors.
30 citations
Patent•
13 Feb 1975
TL;DR: The low pressure braze bonding of members comprised of, for example, titanium and zirconium alloys is accomplished with the use of foil-type braze alloy preforms as discussed by the authors.
Abstract: The low pressure braze bonding of members comprised of, for example, titanium and zirconium alloys is accomplished with the use of foil-type braze alloy preforms. The braze alloy preforms comprise a titanium-zirconium foil which has been coated on at least one side with a layer of nickel which functions as a eutectic depressant alloying agent. Upon heating, at a temperature below the beta transus of titanium, a liquid phase will form and the nickel will partially alloy with and migrate into the foil and workpieces and solidification of the resulting joint may thereafter be obtained.
30 citations