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 article, the development of high strength zirconium alloys is described with particular reference to nuclear applications and the common terms used in the description of ZIRconium and its alloys and the specifications for industrial and nuclear service.
137 citations
TL;DR: In this paper, the physico-chemical properties of zirconium hydride such as mechanical and thermal properties have been studied in the form of pellets (6 mm φ×10 mm l) with hydrogen contents with 1.5-1.7 H/Zr, which were fabricated directly from Zr metal in a modified UHV Sieverts apparatus.
136 citations
TL;DR: The parabolic rate constant for total oxygen consumption increases as the power of the oxygen partial pressure at 1630° and 1760°K as discussed by the authors, when the transition temperature for the monoclinic to tetragonal phase change in, there is a sharp increase in the rate of oxidation.
Abstract: The oxidation of zone melted specimens of and was studied at temperatures of 1200°–2000°K and at oxygen partial pressures of 1–700 Torr in helium. Parabolic rate behavior was observed. For above 1400°K an activation energy of was determined. Below 1400°K the activation energy is much lower, and the mechanism of oxidation is different, probably because of the presence of boron oxide in the condensed phase. Below 1300°K, the parabolic rate constant appears to be directly proportional to oxygen partial pressure; at 1830°K, the rate constant is independent of oxygen pressure. For in the range 1480°–1870°K an activation energy of was observed. Around 1970°K, the transition temperature for the monoclinic to tetragonal phase change in , there is a sharp increase in the rate of oxidation. The parabolic rate constant for total oxygen consumption increases as the power of the oxygen partial pressure at 1630° and 1760°K.
133 citations
TL;DR: The metastable ω-phase in zirconium base alloys has been found to be truly hexagonal with ca = 0.622 ± 0.002 as discussed by the authors.
133 citations
Journal Article•
TL;DR: In this paper, the corrosion behavior of model Zr-based alloys at 500°C is assessed by long term (up to 400 days) corrosion testing in an effort to evaluate their potential for use in the supercritical water reactor and to assess the influence of alloying elements on corrosion behavior.
Abstract: Abstract The corrosion behavior of model Zr-based alloys at 500 °C is assessed by long term (up to 400 days) corrosion testing in an effort to evaluate their potential for use in the supercritical water reactor and to assess the influence of alloying elements on corrosion behavior. The corrosion weight gains from such systematic testing are seen to be a factor of five higher than those measured at 360 °C but the protectiveness ranking of the alloys is similar. Detailed characterization of the oxide layers to rationalize the differences in corrosion behavior was performed using synchrotron radiation and systematic differences are observed in protective and non-protective oxides, especially near the oxide–metal interface. The overall corrosion rate of the best Zr-based alloys compared favorably with those of other alloys being considered for use in the supercritical water reactor.
133 citations