A backup control rod positioned above the core fuel region increases neutron leakage to reduce void reactivity in fast reactors.
A twisted metallic band spacer element maintains distance between fast-neutron reactor fuel rods while reducing metal consumption.
Converting pelletized spent nuclear fuel into halide salt powder to reduce storage space requirements and eliminate long-term waste streams.
Outer partial-length fuel rods lower void fraction to enhance neutron moderation and burnable poison worth, improving shutdown margin.
Model predicts irradiation creep and swelling in breed-and-burn reactors, preventing fuel element distortion during high burn-up cycles.
Varying internal blanket thickness across radial zones flattens power density while increasing coolant outlet temperature for molten salt integration.
A Zr-based alloy with Fe, Cu, and Ta forms a ductile matrix surrounding fuel pellets.
Calculates principal and secondary PCI margins to assess cladding stress in nuclear reactor fuel assemblies.
A threaded spacer distributes plenum spring force across the top fuel pellet surface to maintain uniform pressure.