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10 Modules / ~100 pages
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~25 Modules / ~400 pages

Thermal-Hydraulics in Nuclear Power Plants
( 30 Modules )

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


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