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