Module #1 Introduction to Thermal-Hydraulics Overview of thermal-hydraulics in nuclear power plants, importance and applications
Module #2 Thermodynamic Principles Review of thermodynamic principles, heat transfer and energy conversion
Module #3 Hydraulic Fundamentals Review of hydraulic principles, fluid flow and pressure drop
Module #4 Nuclear Power Plant Systems Overview Overview of nuclear power plant systems, including reactor coolant system and secondary system
Module #5 Thermal-Hydraulic Codes and Models Introduction to thermal-hydraulic codes and models, including RELAP, TRAC and CATHARE
Module #6 Single-Phase Flow Fundamentals Theory of single-phase flow, including laminar and turbulent flow
Module #7 Flow Regimes and Instabilities Flow regimes and instabilities in single-phase flow, including flashing and cavitation
Module #8 Pipe Flow and Losses Pipe flow and losses in single-phase flow, including friction factor and minor losses
Module #9 Component Models Thermal-hydraulic models for single-phase flow components, including pipes, pumps and valves
Module #10 Single-Phase Flow Applications Applications of single-phase flow in nuclear power plants, including coolant flow and emergency core cooling
Module #11 Two-Phase Flow Fundamentals Theory of two-phase flow, including bubble dynamics and flow regimes
Module #12 Two-Phase Flow Models Thermal-hydraulic models for two-phase flow, including drift-flux and two-fluid models
Module #13 Two-Phase Flow Instabilities Instabilities in two-phase flow, including density wave oscillations and flashing
Module #14 Component Models for Two-Phase Flow Thermal-hydraulic models for two-phase flow components, including steam generators and condensers
Module #15 Two-Phase Flow Applications Applications of two-phase flow in nuclear power plants, including boiling water reactors and steam generators
Module #16 Introduction to Nuclear Power Plant Transients Overview of nuclear power plant transients, including design basis accidents and beyond-design basis accidents
Module #17 Loss of Coolant Accidents (LOCA) Thermal-hydraulic analysis of LOCA, including blowdown and refill
Module #18 Transient Analysis Methods Methods for transient analysis, including numerical methods and experimentally-based correlations
Module #19 Transient Applications Applications of transient analysis in nuclear power plants, including safety analysis and design optimization
Module #20 Best-Estimate Plus Uncertainty (BEPU) Methodology BEPU methodology for transient analysis, including uncertainty quantification and sensitivity analysis
Module #21 Multi-Dimensional Thermal-Hydraulics Advanced thermal-hydraulic models, including computational fluid dynamics (CFD) and multi-dimensional models
Module #22 Passive Safety Systems Thermal-hydraulic design and analysis of passive safety systems, including passive cooling systems
Module #23 Small Modular Reactors (SMRs) and Advanced Reactors Thermal-hydraulic design and analysis of SMRs and advanced reactors, including integral pressurized water reactors
Module #24 Thermal-Hydraulic Simulation and Validation Validation of thermal-hydraulic codes and models, including experimental validation and uncertainty quantification
Module #25 Thermal-Hydraulic Challenges in Nuclear Power Plants Current challenges and research areas in thermal-hydraulics for nuclear power plants, including scaling and computational methods
Module #26 Case Study:Pressurized Water Reactor (PWR) Thermal-hydraulic analysis of a PWR, including primary and secondary systems
Module #27 Case Study:Boiling Water Reactor (BWR) Thermal-hydraulic analysis of a BWR, including reactor coolant system and containment
Module #28 Case Study:Advanced Gas-Cooled Reactors (AGR) Thermal-hydraulic analysis of an AGR, including coolant flow and heat transfer
Module #29 Case Study:Small Modular Reactor (SMR) Thermal-hydraulic design and analysis of an SMR, including passive cooling system
Module #30 Course Wrap-Up & Conclusion Planning next steps in Thermal-Hydraulics in Nuclear Power Plants career
