2024 journal article
Evolution of extended defects in UO<sub>2</sub> during high temperature annealing
JOURNAL OF NUCLEAR MATERIALS, 593.
author keywords: Dislocation loop; Bubble; Ion irradiation; Microstructure; Uranium oxide
UN Sustainable Development Goal Categories
6. Clean Water and Sanitation
(OpenAlex)
Source: Web Of Science
Added: May 20, 2024
The evolution of thermophysical characteristics of uranium oxide (UO2) under irradiation is a critical aspect of nuclear fuel performance of light water reactors. This study examines the effect of high-temperature annealing at 1000 °C - 1600 °C on defect evolution in krypton irradiated UO2 at room temperature. Transmission electron microscopy analysis reveals that the size of irradiation-induced bubbles and dislocation loops increases but their density decreases with annealing temperatures. Perfect dislocation loops with b⇀ = <110> dominate, regardless of the annealing temperature. A rate theory model for extended defect evolution is applied to conclude that current understanding of dynamical loop and bubble evolution at high-temperature annealing is governed by defect coalescence.