Categorical Exclusion Determination
Office of NEPA Policy and Compliance
July 13, 2015
Estimated Read Time min
The University of Wisconsin proposes to use an inherent feature of salt- and gas-cooled reactors towards the capture and removal of tritium from the primary coolant system: the presence of the graphite moderator. The objectives of the project are to: 1) Characterize tritium transport in liquid fluoride salts and graphite, 2) demonstrate the in-situ effectiveness of tritium absorption by the graphite fuel elements, and 3) develop a design for a graphite bed tritium filter that can integrate with salt-to-air heat exchangers.