船用核动力（英文版） - 中国高校教材图书网
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书名： |
船用核动力（英文版）
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| ISBN： | 978-7-313-24453-6 |
条码： | |
| 作者： |
于俊崇 编著
相关图书
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装订： | 平装 |
| 印次： | 1-1 |
开本： | 大32开 |
| 定价： |
￥280.00
折扣价：￥266.00
折扣：0.95
节省了14元
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| 出版社： |
上海交通大学出版社 |
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| 出版日期： |
2021-04-01 |
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| 内容简介： |
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。
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| 作者简介： |
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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OO专家，是核动力领域国内OO的专家、技术OO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。
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| 章节目录： |
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
2.6.1 Overview
2.6.2 A Brief Introduction of 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 of 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 of Structure
2.8.3 Reactor Shielding Design
2.8.4 Shielding Materials
2.8.5 Reactor Support Materials
2.8.6 Design Analysis
References
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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
Chapter 11 Reliability and Maintainability Design
Chapter 12 Accident and Safety Analysis
Chapter 13 Operation and Operation Analysis
Chapter 14 Accident Management
Chapter 15 Ageing Management
Chapter 16 Test Verification
Chapter 17 Reactor Loading and Unloading
Chapter 18 Decommissioning of Marine Nuclear Power Plants
Index
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