Our research focuses on the intersection of reactor physics and thermal-hydraulics, utilizing high-performance computing to solve complex safety problems in advanced nuclear reactors.
We focus on developing and optimizing coupled analysis systems that integrate neutronics and thermal-hydraulics. By capturing detailed feedback mechanisms in nuclear reactors using high-fidelity codes (e.g., nTRACER/ESCOT), we aim to ensure precise safety margins for both steady-state and transient conditions.
Development of pin-resolved coupled codes.
Transient analysis of PWRs and SMRs.
Feedback mechanism optimization.
We are dedicated to developing our own in-house codes and enhancing physical models within established industrial codes. Our research includes developing specialized models for the analysis of Gen-IV reactors and systems operating in marine environments.
In-house Code Development
- Subchannel: ESCOT
Established Codes Utilization & Improvement
- System: MARS
Advanced Modeling: Specialized models for Gen-IV systems and marine environments.
We conduct comprehensive safety analyses for advanced nuclear systems including Small Modular Reactors (SMRs) and Generation IV reactors. Our expertise covers transient and accident analysis to evaluate safety margins and system response under various operating conditions.
Safety margin evaluation for innovative SMR designs.
Accident scenario simulation (RIA, LOCA, etc.).
Natural circulation capability assessment for passive safety systems.
To handle the computational burden of high-fidelity simulations, we research advanced deterministic numerical methods and parallel computing techniques. We implement massive parallelization strategies (MPI) and acceleration algorithms.
Anderson Acceleration for fixed-point iteration.
Massively parallel computing optimization.
Efficient linear solver implementation.