1. Thermal-Hydraulic Experiments and Modeling | 열수력 실험 및 모델링

Our research investigates the fundamental mechanisms of boiling heat transfer and critical heat flux (CHF) phenomena under operating pressurized water reactor conditions. We combine high-fidelity experimental techniques with advanced computational methods to develop mechanistic prediction models.

가동 가압 경수형 원자로 조건에서의 비등 열전달 및 임계열유속(CHF) 현상의 기본 메커니즘을 연구합니다. 고충실도 실험 기술과 첨단 전산 방법론을 결합하여 기계론적 예측 모델을 개발합니다.

Key Topics:

• Pool and flow boiling heat transfer characteristics
• Critical heat flux prediction and modeling
• Subcooled boiling and two-phase flow instabilities
• CRUD deposition effects on boiling performance
• Advanced experimental measurement techniques

2. Advanced Reactor Thermal-Hydraulics | 차세대 원자로 열수력

We evaluate the thermal-hydraulic performance and safety characteristics of advanced reactor systems including Small Modular Reactors (SMRs) and Generation-IV concepts. Our approach integrates scaling analysis, integral/separate-effects testing, and system-level safety analysis.

소형모듈형원자로(SMR) 및 4세대 원자로를 포함한 차세대 원자로 시스템의 열수력 성능 및 안전성을 평가합니다. 상사성 분석, 개별효과/종합효과 시험, 시스템 수준 안전 분석을 통합적으로 수행합니다.

Key Topics:

• Scaling methodology for advanced reactor test facilities
• Passive safety system performance evaluation
• System-level thermal-hydraulic code assessment (RELAP, TRACE)
• Printed Circuit Steam Generator (PCSG) thermal-hydraulic analysis
• Fast Modular Reactor (FMR) system analysis