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.
Papers published on a yearly basis
Papers
More filters
TL;DR: The deformation and fracture of Zircaloy-4 and pure zirconium sheets having strong (0002) textures were studied under plane-strain compression at temperatures from 20° to 800°C as discussed by the authors.
51 citations
01 Jan 1960
TL;DR: In this article, the crystal structures in the metallic systems Zr - Pd, Zr- Al, Mo-Al, Mn -Al, Fe-Ga, Pt-Ga and Pd-As are tabulated.
Abstract: Results on the crystal structures in the metallic systems Zr - Pd, Zr- Al, Mo- Al, Mn-Al, Fe-Ga, Pt-Ga, Rh-Si, Ir-Si, Pt-Ge, Pt-Si, and Pd-As are tabulated. (J.S.R.)
51 citations
TL;DR: In this paper, a method of preparing the disilicides of titanium, zirconium, and hafnium is outlined, where unit-cell dimensions, density, Knoop microhardness numbers, chemical analyses and solubility in various reagents are given for the three compounds.
Abstract: A method of preparing the disilicides of titanium, zirconium, and hafnium is outlined. Unit-cell dimensions, density, Knoop microhardness numbers, chemical analyses, and solubility in various reagents are given for the three compounds. It is concluded that these disilicides have no value as industrial hard materials.
50 citations
TL;DR: In this article, the authors performed tube burst tests with artificially hydrided Zircaloy-4 specimens at room temperature and at 620 K. The hydrides were accumulated in the cladding periphery and formed "hydride rim" (radially-localized hydride layer) as observed in high burnup PWR fuel claddings.
Abstract: To promote a better understanding of failure behavior of high burnup PWR fuel rods during reactivity initiated accidents (RIAs), tube burst tests have been performed with artificially hydrided Zircaloy-4 specimens at room temperature and at 620 K. Pressurization rate was increased to a maximum of 3.4 GPa/s in order to simulate rapid pellet/cladding mechanical interaction (PCMI) that occurs in high burnup fuel rods during a pulse-irradiation in the Nuclear Safety Research Reactor (NSRR). Hydrogen content in the specimens ranged from 150 to 1,050 ppm. Hydrides were accumulated in the cladding periphery and formed ‘hydride rim’ (radially-localized hydride layer) as observed in high burnup PWR fuel claddings. The hydrided cladding tubes failed with an axial crack at the room temperature tests. Brittle fracture appeared in the hydride rim, and failure morphology was similar to that observed in the NSRR experiments. The hydrides rim obviously reduced burst pressure and residual hoop strain at the tests. The res...
50 citations
01 Jan 1999
50 citations