CX-270406: Mechanisms of Retention and Transport of Fission Products in Virgin and Irradiated Nuclear Graphite – University of Central Florida

The University of Central Florida, in collaboration with North Carolina State University and Oak Ridge National Laboratory, proposes an integrated experimental-computational approach to measure the diffusivities of seven fission products – Iodine (I), Cesium (Cs), Krypton (Kr), Strontium (Sr), Ruthenium (Ru), Silver (Ag), and Europium (Eu) in five nuclear (virgin/irradiated) graphite grades – HOPG, POCO (ZXF-5Q/AXF-5Q), NBG-18, PCEA, and IG-110, as well as in a representative matrix graphite grade. Using a suite of experimental analysis techniques and multiscale simulations, the project will elucidate the pertinent transport/retention mechanisms of the FPs in the selected graphite grades.