CX-033855: Transient Reactor Test (TREAT) Facility Irradiation of a EBR-II High Burnup Mixed Oxide (MOX) Fuel Pin R2

This revision involves work between Idaho National Laboratory (INL) and the Japan Atomic Energy Agency (JAEA). The goal is to develop a threshold f…

Office of NEPA Policy and Compliance

April 4, 2025
minute read time

This revision involves work between Idaho National Laboratory (INL) and the Japan Atomic Energy Agency (JAEA). The goal is to develop a threshold for fuel-cladding mechanical interaction (FCMI) in irradiated oxide fuels. These thresholds will be used for designing future irradiation experiments in the Japanese experimental fast reactor, JOYO, and for qualifying oxide fuels for future commercial Sodium Fast Reactors (SFRs).