CONTENTS
Module 1. Introduction and Overview of Nuclear Power
1.1 Status and Trends of Nuclear Power in the World
Abstract
1. Introduction
2. Future World Energy Supply and Demand
3. Current Status and Prospects for Nuclear Power
4. Overview of Advanced Reactor Development
4.1 Evolutionary Water Cooled Cooled Reactors
4.2 Innovative Gas, Water and Liquid Metal Colled Systems
4.3 Non-electric Applications
5. Concluding Remarks
References
1.2 Introduction of Koream Nuclear Energy policy
1.3 Planning and Implementation of Nuclear Power Plant Construction
2. Pre-project
2.1 Pre-project Activities
2.2 Bid Specification and Evaluation
2.3 Negotiation and Contract
3. Contruction Execution Phase
3.1 Structure of Project Management
3.2 Project Control
3.3 Interfaces with Project Management
1.4 Experience In Self-Reliance of Nuclear Power Technology
Ⅰ. Korean Nuclear Power Program
Ⅱ. Self-Reliance Program for Nuclear Power Technology
Ⅲ. Technology Transfer
Ⅳ. Long-term Prospective of Nuclear Power Technology
Ⅴ. Summary
1.5 Advanced Integral Reactor Development for Non-electric Applications
1. Overviews
• Trends of Advanced Reactor Development
• Backgrounds and Goals
• Direction of Advanced Reactor Development
• Key Technology for Advanced SMR
• Incentives for SMR Development
• Categorization of SMRs
2. Current Status of SMR Development
• Supercritical Reactor
• Integral Reactor
• Block-type Reactor
3. SMART-Advanced Reactor for Dual Purpose Application
4. Remarks
1.6 Regulatory Activities for Nuclear Power Plant
1. Intorduction
2. Structure of Nuclear Safety Regulation
3. Activities of Regulatory Organizations
4. Nuclear Safety Regulation
5. R&D Program on Nuclear Regulation
6. International Cooperation
7. Future Perspectives and Concluding Remarks
1.7 Korean Next Generation PWR Development
1. Backgrounds
2. Overview of KNGR Project
3. Design Requirements
4. Technical Features
5. Future Outlook
Module 2. Description of Nuclear Power Reactor
2.1 Overview of Korean Standard Nuclear Power Plant Systems
Part 1. KSNP Design Philosophy
Part 2. KSNP Building Configuration
Part 3. KSNP Process System
Part 4. KSNP Design Parameters
Part 5. KSNP Control System
Part 6. Gradual Improvement of KSNP
2.2 Nuclear Steam Supply System (NSSS)
2.2.1 Reactor Coolant System
1.1 Basic PWR - Steam Cycle
1.2 THREE STEP ENERY CONVERSION
1.3 RCS - Three Part System
1.4 KSNP RCS
2. System Function
3. RCS Physical Arrangement
4. RCS Components
4.1 Reactor Vessel
4.2 Reactor Internals
4.3 Steam Generator
4.4 Reactor Coolant Pump
4.5 Pressurizer
5. RCS Penetrations
6. Instrumentation
7. RCS Interfacing System
8. System Operation
9. NSSS Control Concept
2.2.2 Reactor Core and Components
2. Reactor
3. Core Compontents
3.1 Fuel Assemblies and Loading Pattern
3.2 Control Rods
3.3 Burnable Poisons
3.4 Grids
3.5 Instrumentation
4. Core Design Bases
4.1 General
4.2 Excess Reactivity and Fuel Burnup
4.3 Core Design Lifetime and Fuel Replacement Program
4.4 Negative Reactivity Feedback
4.5 Reactivity Coefficient
4.6 Burnable Poison Requirements
4.7 Stability Criteria
4.8 Maximum Controlled Reactivity Insertion Rate
4.9 Power Distribution Control
4.10 Excess CEA Worth with Struck Rod Criteria
4.11 Chemical Shim Control
4.12 Maximum CEA Speeds
Appendix Indigenous Core Design Codes
A. Advanced Core Design Code System - Master
B. PMS / ACE
2.2.3 Engineered safety features action system
1.1 Objectives
1.2 General Overview
2. ESF System Description
2.1 Containment System
2.2 Containment Spray System
2.3 Safety Injection System
2.4 Shutdown Injection System
2.5 Auxiliary Feedwater System
2.6 Safety Depressurization System
2.2 4 Monitoring System
• NSSS I&C Overview
• Monitoring System
• SMART Control Room and Information Level
2.2.5 Plant Protection System
2. Reactor Protection System (RPS)
2.1 RPS Logic
2.2 Trip Functions
3. ESF Actuation System (ESFAS)
3.1 Logic
3.2 ESFAS Functions
4. Operation
2.2.6 Fuel Storage and Handling System
2. Fuel Handling System (FHS)
2.1 FHS Layout
2.2 Refueling Procedures
2.3 Fuel Handling Equipment
2.4 Design Requirements
2.5 Interfaces
3. Fuel Storage Rack
3.1 Design Requirements
3.2 Analysis
3.3 Interfaces
4. Advanced Design Features
2.2.7 Plant control System
• Control Systems
• SMART Control and Signal Level
2.2.8 Chemical and Volume Control System
1. Design Bases
1.1 Functions
1.2 Design Criteria
2. System Description
2.1 Reactor Coolant Inventory Control
2.2 Chemistry and Purity Control
2.3 Reactivity Control
2.4 Reactor Coolant System Pressure Control
3. Component Description
Figure 1. CVCS Flow DiagramⅠ: Letdown and Charging System
Figure 2. CVCS Flow DiagramⅡ : Boron Recycle System
2.2.9 Reactor Engineering
1. Physics Radiation
2. Ex-Core Detector Response Analysis
3. Criticality Safety Analysis
4. Radiation Design Guide
2.3 Nuclear Safety
2.3.1 Safety Analysis
1. Characteristics of Nuclear Reactor Safety
2. Safety Goal
3. General Principle of Reactor Safety
3.1 Multi-Barrier
3.2 Defence-in-Depth
3.3 Quality Assurance : Code and Standards
4. Safety Analysis
4.1 Methodologies of Safety Analysis
4.2 Milestones of Safety Analysis
5. Event / Accident Analysis
5.1 Important Concepts in Event / Accident Analysis
5.2 Event / Accident Categorization
5.3 Event / Accident Analysis Format
6. KSNP Event / Accident Analysis Methodlogy
6.1 Event Classification
6.2 Acceptance and Safety Criteria
6.3 FSAR Chapter and Safety Criteria
6.4 Assumptions for Event / Accident Analysis
6.5 Analysis Code System
6.6 Characteristics of Events
6.7 Analysis Procedure
2.3.2 PSA
1. Overview PSA
2. Fucdamentals of Reliability Analysis
3. Fault Tree and Event Tree Analysis
1) Fault Tree Analysis
2) Event Tree Analysis
4. Procedures of PSA
1) Level 1 PSA
2) Level 2 PSA
3) Level 3 PSA
5. Data Analysis
• Initiating Events
• Hardware Reliability Data
• Human Reliability Data
• Common Casue Failure
• Maintenance Unavailability
6. PSA Applications
• FT modeling for Unscheduled Maintenance Unavailability
• Risk Monitor
Note : This document uses part of information of the following materials.
- IAEA Safety Series No. 50-P-4, 8, 12,
- Reliability Engineering and Risk Analysis, M. Modarres, Marcel Dekker, Inc.
2.4 Fuel Design and Fabrication
2. Fuel Design
2.1 Description of PWR Fuel
2.2 Licensing Requirements
2.3 Functional Requirements
2.4 Design Bases and Criteria
2.5 Design Analysis
3. Fuel Fabrication
3.1 UO2Conversion and Pelletizing Process
3.2 Fuel Rod Manufacturing Process
3.3 Fuel Assembly Manufacturing Process
4. Fuel Development Status
4.1 Current Development Objectives
4.2 Fuel Vendor's Development
2.5 BOP and Turbine / generator System
2.5.1 Main Steam and Feedwater System
Ⅰ. Steam Generator
1 Function
2 Design Description
3 Steam Generator Instrumentation
Ⅱ. Main Steam System
1 System Function
2 Overview
3 Major Components
4 Operation
Ⅲ. Main Feedwater System
Ⅳ. Auxiliary Feedwater System
2.5.2 Turbine / Generator System
1.1 History
1.2 Basic Turbine Theory
1.2.1 Nozzles
1.2.2 Basic Turbine Types
1.2.3 Impulse Turbine
1.2.4 Reaction Turbine
1.3 Function of Turbine Stages
2. Turbine Component
2.1 Classification of Turbines
2.2 Major Centerline Components
2.2.1 Shells and Casings
2.2.2 Nozzle and Diaphragms
2.2.3 Turbine Seals
2.2.4 Turbine Rotors and Buckets
2.2.5 Standards
2.2.6 Bearings
2.2.7 Turning Gear
2.2.8 Shaft Grounding Brushes
2.3 Main Steam Valves
2.3.1 Main Stop Valves
2.3.2 Control Valves
2.4 Auxiliary Steam Valves
2.5 Moisture Separators and Reheaters
3. Turbine Supporting Systems
4. Generator System
4.1 Generator Construction
4.1.1 Generator Stator and Windings
4.1.2 Generator Rotor
4.2 Exciters
4.2.1 Types of Excitation System
4.3 Generator Support Systems
4.3.1 Generator Gas Cooling Systems
2.6 Major Components Design and Manufacturing
2. Reactor Coolant System
3. Design Flow
4. Design Features
4.4 Pressurizer
5. Analysis
6. Manufacturing
Module 3. Operation and Maintenance Experiences of NPP
3.1. Operation and Maintenance Experiences of Nuclear Power Plants
1. Overview of the Korean Nuclear Power Program
• Status of Operation and Maintenance of NPP
• Long-term Power Development Plan
• Technological Self-sufficiency Program
2. Operation Experiences of NPP
• Plant Performance
• Feedback of Operating Experiences
• CANDU Experiences
• Operation Organization
• Nuclear Safety
• Human Resources Training
3. Maintenance Experiences Training
• Maintenance Management
• Maintenance Organization
• Maintenance System and Policy
• Plant Refurbishment
• Outage Management and Reduction
4. Conclusion
3.2 Simulator Trainiing with CNS at KAERI
1. About Simulator
1.1 Introduction
1.2 Simulator
1.3 KAERI-CNS
2. Simulator Malfunction List
3.3. Practice on full-scope simulator at KHNP Nuclear Power Education Center
2. Definitions
3. Goal
4. Simulator Suitability
5. Program Development
6. Conduct of Simulator Training
7. Modification
8. Documentation
9. Introduction of KNPEC Simulator Training Program
10. Instructor Console System
11. List of Scenario
◆ Lecture - Use of Simulator for Training and Assessment
