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Reliable and Robust Artificial intelligence (AI) Framework for Reactor Safety Analysis
Development of physics-informed machine learning (PIML) model
Application of PIML model into system-scale safety analysis codes
Uncertainty quantification and xAI for Trustworthy framework
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
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