本书是“十三五”国家重点图书出版规划项目“核能与核技术出版工程”之一。主要内容包括船用核动力的概貌、反应堆系统、核动力总体及其配套系统、安全分析、运行分析、事故管理、老化管理、试验、装卸料、退役等，系统而全面地介绍了船用核动力研制全过程、全寿期知识。本书可供核能工程领域研究人员参考，也可作为高等学校核专业教学之用。
于俊崇，研究员级高工、博导，中国工程院院士，是中央直接掌握联系的高级专家，是核动力领域国内资深的专家、技术权威及领军人物。一直从事核动力和研究堆的设计研究。曾先后担任型号副总设计师、总设计师。先后获国家科技进步二等奖1项；部级科技进步一等奖3项、二等奖4项、三等奖十余项；全军科技进步一等奖1项，荣立国防科工委A、B工程一等功各一次。
Chapter 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
Chapter 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 of Structure
2．5．3 Materials
2．5．4 Design Analysis and Verification
2．6 Control Rod Drive Mechanism
……
Chapter 3 Reactor Coolant System （RCS）
Chapter 4 Nuclear Auxiliary Systems
Chapter 5 Engineered Safety System
Chapter 6 Instrumentation and Control System
Chapter 7 Steam Power Conversion System
Chapter 8 Source Term and Radiation Protection
Chapter 9 Vibration and Noise Reduction
Chapter 10 Mechanical Analysis and Evaluation
Index
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