An experimental facility has been designed and constructed to investigate vacuum drying of used nuclear fuel for placement in dry cask storage. The motivation for this study was to demonstrate the drying of used nuclear fuel using industry practice and provide the experimental data for development of drying models. A full size BWR fuel assembly (Areva Atrium 10A) with depleted uranium rods and 12 heater rods to simulate decay heat of used fuel is utilized in experiments. The fuel assembly with an interchangeable rod and chamber are designed to examine drying of key features of concern such as failed fuel rods, a BWR water rod, a PWR guide thimble, porous neutron absorber materials, spacer disks, etc. The vacuum chamber simulating the storage cask contains structure similar to baskets for the fuel assembly and surrounding rails to center in the chamber. A test plan is currently being executed and involving separate effects tests of individual features and combined tests with selected features to provide data for the development of drying models to describe drying as a function of cask variables such as temperature, pressure, and relative humidity. The experimental plan follows typical industry practice of vacuum drying in stages stepping down in pressure and separated by hold times to provide indication of excess water retained by observation of pressure rise due to boiling of water.