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 contact angles of Zr-Ni, ZrCu and ZrCo alloys against PSZ were measured by the sessile drop method, and the fracture shear strength of this joint was 55 MPa.
Abstract: The contact angles of Zr-Ni, Zr-Cu and Zr-Co alloys against PSZ were measured by the sessile drop method. Each alloy wetted PSZ very well. Zr-Co alloys showed a different behaviour. Joints of PSZ plates were obtained using Zr-17Ni alloy. At the joint interface, internal oxidation of zirconium occurred. The fracture shear strength of this joint was 55 MPa.
28 citations
TL;DR: In this paper, a series of single rod tests was performed at KIT in framework of the new QUENCH-LOCA programme to investigate the properties of Zircaloy-4 claddings hydrogenated at temperatures of 900, 1000, 1100, and 1200 K to hydrogen contents between 600 and 10,000 Wppm H.
28 citations
Patent•
25 May 1989TL;DR: In this article, a nuclear fuel element for use in the core of a nuclear reactor is disclosed having an improved corrosion resistant cladding, which is comprised of zirconium alloys containing in weight percent 0.5 to 2.
Abstract: A nuclear fuel element for use in the core of a nuclear reactor is disclosed having an improved corrosion resistant cladding. The cladding is comprised of zirconium alloys containing in weight percent 0.5 to 2.0 percent tin, or 0.5 to 2.5 percent bismuth, or 0.5 to 2.5 percent bismuth and tin, and about 0.5 to 1.0 percent of a solute composed of a member selected from the group consisting of molybdenum, niobium, tellurium and mixtures thereof, and the balance zirconium. Composite claddings are disclosed having a surface layer of one of the corrosion resistant zirconium alloys metallurgically bonded to a Zircaloy alloy tube. Claddings may contain an inner barrier layer of a moderate purity zirconium metallurgically bonded on the inside surface of the cladding to provide protection from fission products and gaseous impurities generated by the enclosed nuclear fuel.
28 citations