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, the microstructures of annealed zirconium, zircaloy-2 and Zr-2.5 wt% Nb containing α' were studied after neutron irradiation to fluences of ≈1 × 1025 n/m2, > 0.1 MeV, in the temperature range 573 to 923 K.
71 citations
Patent•
27 Mar 1998TL;DR: An oxide coating is formed on zirconium or ZIRconium alloys of refined microstructure by a process comprising at least the step of inducing an appropriate altered surface roughness such that subsequent oxidation results in a uniformly thick oxide coating as mentioned in this paper.
Abstract: An oxide coating is formed on zirconium or zirconium alloys of refined microstructure by a process comprising at least the step of inducing an appropriate altered surface roughness such that subsequent oxidation results in a uniformly thick oxide coating. An oxide coating of uniform and controlled thickness is especially useful on orthopedic implants of zirconium or zirconium-based alloys to provide low friction, highly wear resistant surfaces on artificial joints, such as hip joints, knee joints, elbows, etc. The uniformly thick oxide coating of controlled depth on oxide coated prostheses provides a barrier against implant corrosion caused by ionization of the metal prosthesis.
70 citations
TL;DR: ZrCo1−xNix (x = 0, 0.2 and 0.3) alloys were prepared and their hydrogen storage behavior were studied in this article, where a van't Hoff plot was constructed using plateau pressure data of each pressure-composition isotherm and the thermodynamic parameters were calculated for desorption of hydrogen in the ZrCo 1−x Nix-H2 systems.
70 citations
TL;DR: In this paper, the formation of the Cu10Zr7 phase in the glassy matrix of a high-strength Cu50Zr30Ti10Nb10 bulk alloy upon solidification led to higher Young's modulus and enhanced ductility of such a composite compared to Cu-based glassy alloys.
Abstract: Low ductility of glassy alloys prevents their technical application as structural materials. In this work, we study the Cu-based crystal-glassy composite material with good mechanical properties. Formation of the Cu10Zr7 phase in the glassy matrix of a high-strength Cu50Zr30Ti10Nb10 bulk alloy upon solidification led to higher Young’s modulus and enhanced ductility of such a composite compared to Cu-based glassy alloys. The as-cast structure was studied by x-ray diffraction and scanning electron microscopy.
70 citations
TL;DR: An advanced Zircaloy cladding containing niobium has been developed and tested extensively both in long-term out-of-pile autoclave exposures and through high burnup irradiation in a pressurized water reactor (PWR) environment.
Abstract: An advanced Zircaloy cladding containing niobium has been developed and tested extensively both in long-term out-of-pile autoclave exposures and through high burnup irradiation in a pressurized water reactor (PWR) environment. Tubing of zirconium-based binary alloys containing 0.5, 1.0, and 2.5% niobium, and a quaternary composition containing tin, niobium, and iron was fabricated in such a manner that the second phase was fully precipitated, but with minimal particle growth. Autoclave testing in pure water and steam over the temperature range of 589 to 727 K indicates that all of the alloys except the 0.5% Nb have a lower post-transition corrosion rate than does Zircaloy-4, with the relative benefit increasing with temperature. Additional autoclave testing in LiOH solutions indicated a marked sensitivity of the Nb binaries to accelerated corrosion, and in these solutions only the Sn-Nb-Fe alloy was superior to Zircaloy-4. Experimental fuel assemblies with cladding of the advanced alloys were examined after one, three, and four cycles in the BR-3 reactor. Rod average burnups of up to 71 GWD/MTU were obtained with total residence times of up to 66 months. Results of post-irradiation examinations are given only for the Sn-Nb-Fe alloy as compared to Zircaloy-4. These examinations revealed that the Sn-Nb-Fe alloy showed the lowest overall corrosion, up to 50% better than Zircaloy-4 at the highest burnups, and was superior to the Zr-Nb binaries. The Sn-Nb-Fe alloy, called ZIRLO, also displayed lower irradiation growth and creep than the others.
70 citations