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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01 Jan 2012
TL;DR: The current alloys are the Zircaloy (Zr, Sn, O++TM) and the Zr, Nb, O) alloys as discussed by the authors.
Abstract: Zirconium alloys have been developed as structural and cladding materials for thermal water reactors, thanks to their low neutron capture cross-section. Alloyed with Sn, Nb, O, and minute amounts of other elements such as the transition metals, they exhibit satisfactory engineering properties. The current alloys are the Zircaloy (Zr, Sn, O + TM) and the (Zr, Nb, O) alloys. New alloys based on combinations of these are being currently implemented. Engineering properties before irradiation are composition and microstructure dependent, and can be adjusted for different components of the nuclear core accordingly.
68 citations
TL;DR: In this article, the microstructure of annealed crystal-bar zirconium, sponge and Zircaloy-2 and -4 has been analyzed following neutron irradiation in EBR II over the temperature range of 644-710 K for neutron fluences up to 6 − x 10 25 n m−2 (E>1 MeV ).
68 citations
TL;DR: In this paper, the authors collected the creep data of Nb-modified zirconium alloys from the open literature as well as their own study over a wide range of stresses and temperatures.
68 citations
TL;DR: In this paper, in situ Electrochemical Impedance Spectroscopy (EIS) and ex-situ microscopic observations have been fitted to a transfer function derived from the Mixed Conduction Model.
67 citations
TL;DR: In this article, the microstructure and low cycle fatigue (LCF) behavior of Al 3 Zr grain-refined AlZnMg alloy were investigated.
67 citations