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This course is designed to review the design basis and layout of the major PWR plant systems. The interactions between the different systems and overall plant integration is discussed in detail.
DAY 1
- Course Introduction
- Introduction to Reactor
- Theory Neutron physics principles and reactor theory
- Core feedback
- Thermal hydraulics of the PWR core and heat exchanger
DAY 2
- Reactor Coolant System
- Reactor Vessel and Core
- Steam Generator
- Reactor Coolant Pump
- Pressurizer
- Chemical and Volume Control System
- Make-up
- Boron Recycle
- Boron Thermal Regeneration
DAY 3
- Residual Heat Removal System
- Balance of Plant Systems
- Main Steam and Turbine
- Main Feedwater and Condenser
DAY 4
- Reactor Trip and Protection System Actuation Logic
- Engineered Safety Features Description
- Emergency Core Cooling System
- Auxiliary Feedwater
- Containment Systems Instrumentation & Control Systems
- Resistance Temperature Detectors
- Incore and Excore Nuclear Instrumentation
- Pressure, DP and Level Measurements
- Rod Control System
- Steam Dump
- Pressurizer Level and Pressure Control
- Steam Generator Water Level Control
DAY 5
- Accident Analysis
- FSAR
- Technical Specification
- Plant Operations
- Three Mile Island and Fukushima
- Questions and Answers
