Research

Application of artificial intelligence (AI) technique for nuclear reactor analysis

• Development of physics-informed machine learning (PIML) model

• Application of PIML model into system-scale safety analysis codes

• AI framework for real-time simulation by reduced order modeling (ROM)

• Development of SMR Prognostic/diagnostic platform

Experimental investigation for thermal-hydraulic phenomena inside the nuclear reactor

• Boiling/condensation/flooding

• Critical heat flux (CHF)

• Post-CHF (Inverted annular film boiling/inverted slug film boiling/dispersed flow film boiling)

• Multidimensional natural circulation

Deterministic safety assessment of nuclear reactors to verify the system safety

• Analysis of Design basis accidents (DBA) and Design extension condition (DEC) 

• Improvement of system-scale thermal-hydraulic analysis codes - MARS, SPACE, TRACE, etc.

• Development of "new component modules" in the safety analysis codes

Design of innovative systems for improved safety and wide application of nuclear energy

• Heat pipe-based safety systems and facilities 

• Heat pipe-based microreactors

• Passive (natural circulation-based) safety systems