Search results for "Zirconium alloy"

Determination of Zircaloy -4 Radiocristallographic Elastic Constants from Room Temperature to 300°C

2000

A new experimental apparatus, allowing the determination of radiocristallographic elastic constants (REC) as a function of the temperature is presented. The material studied the zirconium alloy Zircaloy-4, showing low elastic anisotropy, an isotropic treatment of the problem is possible. As a consequence, the classical sin 2 ψ method is used to determine the REC from room temperature to 300°C.

A Double-Blind Randomized Controlled Trial (RCT) of Titanium-13Zirconium versus Titanium Grade IV Small-Diameter Bone Level Implants in Edentulous Ma…

2012

Background: The use of endosseous dental implants has become common practice for the rehabilitation of edentulous patients, and a two-implant overdenture has been recommended as the standard of care. The use of small-diameter implants may extend treatment options and reduce the necessity for bone augmentation. However, the mechanical strength of titanium is limited, so titanium alloys with greater tensile and fatigue strength may be preferable. Purpose: This randomized, controlled, double-blind, multicenter study investigated in a split-mouth model whether small-diameter implants made from Titanium-13Zirconium alloy (TiZr, Roxolid™) perform at least as well as Titanium Grade IV implants. Me…

Study of stress effects in the oxidation of Zircaloy-4

2001

Abstract The oxidation of zirconium alloy Zy-4 is due to an anionic diffusion of oxygen leading to the formation of an oxide layer of zirconia. According to the Pilling and Bedworth ratio of the Zr/ZrO 2 system, the oxide scale is under compressive stresses. This stress state may play an important role during the corrosion process, from the phases as well as from the kinetics point of view. In order to better understand the eventual relationship between oxide phases, oxidation kinetics and stresses, an experimental apparatus was developed in our laboratory. It allows the application of external tensile stresses, in situ oxidation of the sample in controlled environment and X-ray diffraction…

Texture Effects on Zircaloy Oxidation : Experiment and Simulation

2002

In situ XRD analysis of the oxide layers formed by oxidation at 743 K on Zircaloy 4 and Zr–1NbO

2000

Abstract Two alloys, having different oxidation behaviour (Zy4 and Zr–1NbO), have been investigated during oxidation at high temperature (743 K) and low oxygen pressure (10 kPa) by in situ X-ray diffraction (XRD). Tetragonal phase content and ‘pseudo-stresses’ on the monoclinic phase have been measured as a function of the oxide layer thickness. The tetragonal phase contents are similar for both alloys and decreased with the oxide layer thickness. Pseudo-stresses were much more compressive on Zr–1NbO alloy, with limited changes at the corrosion kinetics transition. On cooling, the tetragonal fractions do not change, while ‘pseudo-stresses’ decreased in different ways for the two alloys. Wit…

Transmission of very slow neutrons through material foils and its influence on the design of ultracold neutron sources

2009

At the Paul Scherrer Institute (PSI), a very intense source of ultracold neutrons (UCN) is being built. The UCN converter of solid deuterium must be contained in a vessel. Produced UCN leave that vessel through its top lid. To decide on the design of the vessel and the top lid, we have measured the transmission of neutrons with velocities between 3 and 20 m/s through different material foils. Contrary to expectations, we found that transmission through aluminium and aluminium alloys is equal or even higher compared to zirconium and reactor-grade zirconium alloys, respectively.

Study of the fuel/clad bonding of pressurized water reactors fuel rods

2017

Durability and integrity of materials used in nuclear power plants is a continuous concern of the nuclear power plant owners and developers. During the fuel irradiation in pressurised water reactors (PWR), the whole fuel-clad assembly is subjected to several irradiation-induced modifications. In particular, the fuel element expansion concomitant to the cladding creeping, leads to the contacting of both materials, allowing the oxidation of the inner side of the clad, locally at first, then tending to affect the overall cladding inner surface. At high burnup, a bonding of the fuel periphery with the metallic cladding can be observed, forming the fuel-clad bonding phenomenon, which conditions …