Marine Nuclear Power Technology

Preface
Acknowledgements
Contents
1 Overview
1.1 Introduction
1.2 Basic Types of Nuclear Power Ships
1.2.1 Nuclear Submarines
1.2.2 Nuclear-Powered Aircraft Carriers
1.2.3 Nuclear-Powered Cruisers
1.2.4 Nuclear-Powered Deep-Sea Facilities
1.2.5 Nuclear-Powered Icebreakers
1.2.6 Nuclear-Powered Merchant Ships
1.3 Design Characteristics and Development Trends of Marine Nuclear Power Plants
1.3.1 Design Characteristics
1.3.2 Development Trends
Reference
2 Nuclear Reactors
2.1 Overview
2.2 Nuclear Reactor Physics
2.2.1 Theory of Nuclear Reactor Physics
2.2.2 Reactor Nuclear Design
2.2.3 Software for Reactor Nuclear Design
2.2.4 Design Verification
2.3 Reactor Thermo-Hydraulics
2.3.1 Overview
2.3.2 Reactor Heat Transfer Theory
2.3.3 Reactor Hydraulics
2.3.4 Reactor Thermo-Hydraulic Design
2.3.5 Reactor Thermo-Hydraulic Test
2.4 Fuel Assembly and Core Components
2.4.1 Fuel Assembly
2.4.2 Core Components
2.5 Reactor Pressure Vessel
2.5.1 Overview
2.5.2 A Brief Introduction to Structure
2.5.3 Materials
2.5.4 Design Analysis and Verification
2.6 Control Rod Drive Mechanism
2.6.1 Overview
2.6.2 A Brief Introduction to Structure
2.6.3 Materials
2.6.4 Design Analysis and Verification
2.7 Reactor Internals
2.7.1 Overview
2.7.2 A Brief Introduction to Structure
2.7.3 Materials
2.7.4 Design Analysis and Verification
2.8 Reactor Support and Shielding
2.8.1 Overview
2.8.2 A Brief Introduction to Structure
2.8.3 Reactor Shielding Design
2.8.4 Shielding Materials
2.8.5 Reactor Support Materials
2.8.6 Design Analysis
References
3 Reactor Coolant System (RCS)
3.1 Overview
3.1.1 Functions
3.1.2 System Composition
3.1.3 System Process
3.2 Design Requirements
3.3 System Arrangement
3.3.1 Separated Arrangement
3.3.2 Compact Arrangement
3.3.3 Integrated Arrangement
3.4 Characteristic Design
3.4.1 Operation Scheme with Constant Average Coolant Temperature
3.4.2 Operation Scheme with Constant Steam Pressure
3.4.3 Compromised Solution
3.4.4 Static Characteristics of Once-Through Steam Generator
3.5 Brief Introduction to Main Equipment
3.5.1 Steam Generator
3.5.2 Reactor Coolant Pump
3.5.3 Reactor Coolant Piping
3.6 Reactor Coolant Water Chemistry
References
4 Nuclear Auxiliary Systems
4.1 Overview
4.2 Pressure Safety System
4.2.1 System Description
4.2.2 Equipment Description
4.3 Residual Heat Removal System
4.3.1 System Description
4.3.2 Equipment Description
4.4 Coolant-Charging System
4.4.1 System Description
4.4.2 Equipment Description
4.5 Component Cooling Water System
4.5.1 System Description
4.5.2 Equipment Description
4.6 Coolant Purification System
4.6.1 System Description
4.6.2 Equipment Description
4.7 Valves
4.7.1 Overview
4.7.2 Shut-off Valves
4.7.3 Safety Valves
4.7.4 Check Valves
4.7.5 Regulating Valves
4.7.6 Valve Reliability
References
5 Engineered Safety System
5.1 Overview
5.1.1 Design Principles for Engineered Safety System
5.1.2 Basis for Determining Engineered Safety System
5.1.3 Design Characteristics of Engineered Safety System of Marine Nuclear Power Plants
5.2 Emergency Core Cooling System
5.2.1 Safety Injection System
5.2.2 Emergency Residual Heat Removal System
5.3 Reactor Compartment Heat Removal System
5.4 Dehydrogenation System
5.5 Backup Reactor Shutdown System
5.6 Case Analysis of Design Flow of Safety Injection System
References
6 Instrumentation and Control System
6.1 Overview
6.1.1 Functions of I&C System
6.1.2 Design Principles
6.1.3 Overall Structure and Characteristics
6.2 Nuclear Measurement System
6.2.1 System Functions
6.2.2 Basic Principle of Ex-core Nuclear Measurement Detectors
6.2.3 Description of the System and Equipment
6.3 Process Measurement and Control System
6.3.1 Process Measurement System
6.3.2 Process Control System
6.4 Reactor Power Control System
6.4.1 System Functions
6.4.2 Principles of Reactor Power Regulation
6.4.3 Design Constraints
6.4.4 Description of the System and Equipment
6.5 Reactor Protection System
6.5.1 System Functions
6.5.2 System Design Principles
6.5.3 System and Equipment Description
6.6 Control Rod Control and Rod Position Measuring System
6.6.1 Functions
6.6.2 System and Equipment Description
6.7 Electrical Control System for Pumps and Valves
6.7.1 System Functions
6.7.2 System and Equipment Description
6.8 Man-Machine Information Display and Operation System
6.8.1 Functions
6.8.2 System Design Principles
6.8.3 System and Equipment Description
6.9 Digitization of I&C System
6.9.1 Technological Development Overview
6.9.2 Technical Schemes of Digital I&C System
References
7 Steam Power Conversion System
7.1 Overview
7.2 Steam System
7.2.1 System Description
7.2.2 Equipment Description
7.2.3 System Operation
7.3 Condensate and Feedwater System
7.3.1 System Description
7.3.2 Equipment Description
7.3.3 System Operation
7.4 Steam Dump System
7.4.1 System Description
7.4.2 Equipment Description
7.5 Circulating Cooling Water System
7.6 Steam Turbine-Gear Unit
7.6.1 Turbines
7.6.2 Gear Reducer
7.7 Turbo-Generator Set
Reference
8 Source Term and Radiation Protection
8.1 Concept and Principles of Radiation Protection
8.1.1 Concept of Radiation Protection
8.1.2 Ionization Radiation Source of Nuclear Power Plants
8.1.3 Basic Principles of Radiation Protection
8.1.4 Dose Limit for Radiation Protection
8.1.5 Design Principles for Radiation Protection of Marine Nuclear Power Plant
8.1.6 Characteristics of Radiation Protection for Marine Nuclear Power Plant
8.2 Source Term Design
8.2.1 Overview
8.2.2 Source Terms Under Normal Operation
8.2.3 Source Terms in Accidents
8.3 Radiation Protection Facilities
8.4 Management of Radiation Protection Work
8.4.1 Control Through Radiation Zoning
8.4.2 Emergency Plan
8.4.3 Radiation Protection Requirements for Nuclear Power Plant at Each Stage
References
9 Vibration and Noise Reduction
9.1 Overview
9.2 Sources and Transfer Paths of the Vibration Noise
9.3 Control Measures for Vibration Noise
9.3.1 Control Measures for Vibration Noise
9.3.2 Vibration Isolation of Transfer Paths
References
10 Mechanical Analysis and Evaluation
10.1 Overview
10.2 Main Theories of Mechanical Analysis
10.2.1 Analysis Theory for Shock Resistance of System and Equipment
10.2.2 Analysis Theory for Structural Stress
10.3 Main Methods for Mechanical Analysis
10.3.1 Theoretical Analysis
10.3.2 Finite Element Method
10.3.3 Experimental Research Methods
10.4 Main Content of Mechanical Analysis
10.4.1 Load Distribution of Systems and Equipment
10.4.2 Stress Analysis for Structures and Components
10.5 Analysis and Evaluation
10.5.1 Load Distribution of Systems and Equipment
10.5.2 Stress Analysis of Structures and Components
10.5.3 Analysis Example
References
11 Reliability and Maintainability Design
11.1 Overview
11.2 Reliability and Maintainability Management
11.3 Reliability Design and Analysis
11.3.1 Reliability Requirements
11.3.2 Methods for Reliability Design
11.4 Design and Analysis of Maintainability
11.4.1 Maintainability Requirements
11.4.2 Qualitative Maintainability Design
11.4.3 Allocation and Prediction of Maintainability
11.5 Tests and Evaluation of Reliability
11.5.1 Environmental Stress Screening Test
11.5.2 Reliability Growth Test
11.5.3 Reliability Qualification Test and Reliability Acceptance Test
References
12 Accident and Safety Analysis
12.1 Overview
12.2 Accident Analysis Methods
12.2.1 Deterministic Accident Analysis
12.2.2 Probabilistic Safety Analysis
12.3 Classification and Analysis Requirements for Design Basis Accidents
12.3.1 Accident Classification and Limit Criteria
12.3.2 Reactivity Insertion Accidents
12.3.3 Loss-of-Flow Accidents
12.3.4 Loss of Heat Sink Accidents
12.3.5 Steam Generator Tube Ruptures
12.3.6 Loss of Coolant Accidents
12.3.7 Ship Blackout Accidents
12.3.8 Anticipated Transients Without Scram
12.4 Accident Analysis Cases
12.4.1 Causes of Ship Blackout Accidents
12.4.2 Frequency of Occurrence and Limiting Criteria of Ship Blackout Accidents
12.4.3 Analysis Methods and Assumptions of Ship Blackout Accidents
12.4.4 Analysis Results of Ship Blackout Accidents
12.4.5 Severe Accidents
12.4.6 Major Phenomena and Processes of Severe Accidents
12.4.7 Severe Accident Prevention and Mitigation
Reference
13 Operation and Operation Analysis
13.1 Overview
13.2 Operation
13.2.1 Initial Cold Start-Up
13.2.2 Normal Cold Start-Up
13.2.3 Steady-Power Operation
13.2.4 Variable Condition Operation
13.2.5 Natural-Circulation Operation
13.2.6 Cold Shutdown of Reactor System
13.2.7 Hot Shutdown and Hot Start-Up of Reactor System
13.2.8 Reactor Operation Under Abnormal Conditions
13.3 Operation Analysis of Reactor Accident Conditions
13.3.1 Purpose
13.3.2 Methods
13.3.3 Content
13.4 Operation Analysis Cases
13.4.1 Analysis of Transition Between Forced Circulation and Natural Circulation
13.4.2 Operation Analysis of LOCAs
References
14 Accident Management
14.1 Overview
14.2 Objectives of the Accident Management
14.3 Accident Management Methods
14.4 Objects of Accident Management
14.5 Diagnostic Methods for Thermo-Hydraulic Phenomena in Typical Accidents
14.6 Emergency Response to Accidents
15 Ageing Management
15.1 Concept of Ageing Management
15.1.1 Concept of Ageing and Its Management
15.1.2 Method for Systematic Ageing Management
15.1.3 Relationship Between Ageing Management and Current Operation Management
15.1.4 Purposes and Significance of Ageing Management of Marine Nuclear Power Plants
15.2 Status of Ageing Management
15.3 Strategies for Ageing Management
15.3.1 Overview
15.3.2 Design
15.3.3 Fabrication and Construction
15.3.4 Commissioning
15.3.5 Operation
15.3.6 Decommissioning
15.4 Ageing Management During Operation
15.4.1 Screening of Ageing-Sensitive Systems and Equipment
15.4.2 Ageing Management Program for Marine Nuclear Power Plants
15.4.3 Aging Mechanism Analysis for Aging-Sensitive Equipment
15.4.4 Equipment Ageing Management Program
15.4.5 Data Collection and Retention for Ageing Management
15.4.6 Actual Status Evaluation of Ageing-Sensitive Equipment
15.4.7 Ageing Management Review
15.5 Application of Ageing Management in Lifetime Extension
15.5.1 Application of Ageing Management Results in the Demonstration of Lifetime Extension
15.5.2 Requirements of Ageing Management in the Extended Lifetime
16 Test Verification
16.1 Overview
16.2 Classification of Tests for Marine Nuclear Power Plant
16.3 Comprehensive Verification Tests of Systems
16.3.1 Function of Comprehensive Verification Tests of Systems
16.3.2 Content of Comprehensive Verification Tests of Systems
16.4 Reactor Physical Start-Up Tests
16.4.1 Definition of Physical Start-Up Tests
16.4.2 Stages of Physical Start-Up Test
16.4.3 Brief Introduction of Physical Start-Up Test
16.5 Mooring Tests and Sea Trials
16.5.1 Overview
16.5.2 Mooring Tests
16.5.3 Sea Trials
16.6 Engineering Assessment Tests of Prototype Reactors
16.6.1 Significance and Role of Prototype Reactors
16.6.2 Content of Engineering Assessment Tests of Prototype Reactors
16.6.3 Development of Prototype Reactors
16.6.4 Development Trend of Prototype Reactors
16.7 Virtual Tests and Digital Reactor System Simulation Verification
16.7.1 Virtual Tests
16.7.2 Definition and Role of Digital Reactors
16.7.3 Overview of Digital Reactor Research
16.7.4 Technical Route of the Digital Reactor Development
References
17 Reactor Loading and Unloading
17.1 Overview
17.1.1 System Functions
17.1.2 System Composition
17.1.3 Main Process Flow
17.1.4 Design Principles
17.2 Reactor Fuel Loading
17.2.1 Reactor Fuel Loading Technology
17.2.2 Reactor Fuel Loading Process
17.2.3 Main Equipment for Reactor Loading
17.3 Reactor Fuel Unloading
17.3.1 Reactor Fuel Unloading Technology
17.3.2 Reactor Fuel Unloading Process
17.3.3 Main Reactor Fuel Unloading Equipment
17.4 Design of Reactor Refueling
17.4.1 Selection of Materials
17.4.2 Cooling Design
17.4.3 Criticality Safety Evaluation
17.4.4 Industrial Safety Design
17.4.5 Design of Radiation Protection Safety
18 Decommissioning of Marine Nuclear Power Plants
18.1 Overview
18.2 Decommissioning Scheme Study
18.2.1 Decommissioning Schemes in Foreign Countries
18.2.2 Decommissioning Scheme in China
18.3 Study on the Status of Nuclear Power Plant Before Decommissioning
18.3.1 Investigation of Reactor Operation History
18.3.2 Calculation and Measurement of Residual Radioactivity
18.3.3 Calculation of Reactor Residual Heat Release and Measurement of Related Temperature
18.3.4 Inspection of Reactor Control Rod Positions
18.3.5 Tests of Performance of Pumps, Valves and Systems
18.4 Reactor Decommissioning
18.4.1 Decommissioning Procedure
18.4.2 On-site Condition Preparation
18.4.3 Reactor Unloading
18.4.4 Decontamination
18.5 Decommissioning of Circuit Systems and Other Equipment in the Reactor Compartment
18.6 Treatment of Radioactive Wastes
18.7 Radiation Protection and Safety
18.7.1 Classification and Management of Work Place
18.7.2 Management of Operators
18.7.3 Safety Measures for Radiation Protection
18.7.4 Strengthening of Radiation Monitoring
Index