ENGPHYS 718
Reactor Heat Transport System Simulation and Analysis
Winter
Topics
- Two-fluid phase modeling
- Thermal-hydraulic phenomena
- Reactor heat transport system
- Modeling and simulation of postulated accidents
- Simulation methodology and tools
- Development and qualification of selected thermal-hydraulics computer codes
- Two-fluid modeling
- Nodalization schemes and numerical methods
- Computer code development
- CATHENA computer code theory and numerical algorithm
- Is a simulation-based course
- It includes CATHENA training
- CATHENA code simulation and analysis
- Preparing a CATHENA model and report
Readings
- “The Essential CANDU: A Textbook on the CANDU Nuclear Power Plant Technology”, “Chapter 7: Thermal- hydraulic Analysis”, UNENE/COG, 2017.
- CATHENA Computer Code Manuals.