Uranium Dioxide-Cladding Interactions. Axial Expansion of UO2 Column in Fuel Elements
- 1 November 1963
- journal article
- research article
- Published by Taylor & Francis in Nuclear Science and Engineering
- Vol. 17 (3) , 381-391
- https://doi.org/10.13182/nse63-a17386
Abstract
Irradiation experiments have been conducted to determine the axial expansion of UO2 in fuel elements. The experiments included fuel segments with 304 stainless and Zircaloy-2 sheaths in self-supporting tubular geometries under boiling water conditions, as well as fuel elements with 304 stainless UO2-supported geometries under superheated steam conditions. The relative UO2 expansion during irradiation was measured by mechanical devices included in the fuel segments and by visual and other observations.Keywords
This publication has 2 references indexed in Scilit:
- The plastic deformation of uranium oxides above 800° CJournal of Nuclear Materials, 1959
- Effect of Particle Size on Bulk Density and Strength Properties of Uranium Dioxide SpecimensJournal of the American Ceramic Society, 1956