NEUP CINRII-25-34072: Reduction, Mitigation, and Disposal Strategies for the Graphite Waste of High Temperature Reactors

Our current IRP, and proposed continuation, seek to enable advanced reactors through development of economically attractive and environmentally sound i-graphite management strategies. The tools and techniques developed thus far to investigate irradiated block graphite are directly applicable to non-fueled matrix graphite, an important area not presently investigated in detail. This continuation will provide our team the opportunity to extend and incorporate matrix graphite activities.

Additional Info

Field	Value
Awarded Institution	State University of New York, Stony Brook
PI	Lance Snead