Abstract and subjects
The objective of this article is to introduce and illustrate the material properties of zirconium-alloyed metallic fuel (U-Zr or U-Pu-Zr alloys). Metallic fuel was used in research reactors, such as the Experimental Breeder Reactor, and is planned for use in the versatile test reactor. A good way to begin understanding metallic fuel properties is to view the topic through the lens of a fuel performance analyst, whose job it is to forecast via computer simulation the temperature, movement, and composition of nuclear fuel as it's irradiated. To do this an analyst uses mathematical representations of fuel properties, called material models, that represent the fuel's thermal and mechanical response. These material models are presented here by showing them in a graphical form, which demonstrates how these properties change with temperature and irradiation. Presenting metallic fuel properties in this way provides the requisite basic knowledge for further research and better understanding when discussing or making decisions about nuclear fuel.