Thermal-hydraulics, nuclear fuel, and reactor safety.

Melt-jet breakup, two-phase mixing, vapor generation, fragmentation, debris formation, and coolability.

Transient cooling and rewetting of high-temperature surfaces and fuel-cladding systems under accident-relevant conditions.

Thermal-hydraulic mechanisms governing fuel-fragment transport, interaction with coolant, and dispersal behavior.

Thermal response, quenching behavior, oxidation/degradation, and mechanical integrity of Cr-coated zirconium-alloy cladding.

Performance of SiC-based composite cladding architectures, including Cr-coated concepts, under normal and accident conditions.

Severe-accident progression and source-term analysis for light-water and advanced reactor systems.

Experimental and system-level analysis of passive reactor-vessel and cavity cooling concepts for advanced reactors.