本書是“十三五”國家重點圖書出版規(guī)劃項目“核能與核技術(shù)出版工程”之一。主要內(nèi)容包括船用核動力的概貌、反應(yīng)堆系統(tǒng)、核動力總體及其配套系統(tǒng)、安全分析、運行分析、事故管理、老化管理、試驗、裝卸料、退役等，系統(tǒng)而全面地介紹了船用核動力研制全過程、全壽期知識。本書可供核能工程領(lǐng)域研究人員參考，也可作為高等學(xué)校核專業(yè)教學(xué)之用。
于俊崇，研究員級高工、博導(dǎo)，中國工程院院士，是中央直接掌握聯(lián)系的高級專家，是核動力領(lǐng)域國內(nèi)資深的專家、技術(shù)權(quán)威及領(lǐng)軍人物。一直從事核動力和研究堆的設(shè)計研究。曾先后擔任型號副總設(shè)計師、總設(shè)計師。先后獲國家科技進步二等獎1項；部級科技進步一等獎3項、二等獎4項、三等獎十余項；全軍科技進步一等獎1項，榮立國防科工委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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