Pressurized Water Reactors

1st Edition - July 8, 2024
Editors: Yurugi Kanzaki, Hidehito Mimaki, Tomofumi Yamamoto
Language: English
Paperback ISBN:
9 7 8 - 0 - 1 2 - 8 2 3 5 8 3 - 6
eBook ISBN:
9 7 8 - 0 - 1 2 - 8 2 3 5 8 4 - 3

Pressurized Water Reactors is the sixth volume in the JSME Series on Thermal and Nuclear Power Generation. In this volume, series editor Yasuo Koizumi and his volume editors, Hi… Read more

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Pressurized Water Reactors is the sixth volume in the JSME Series on Thermal and Nuclear Power Generation. In this volume, series editor Yasuo Koizumi and his volume editors, Hidehito Mimaki, Yurugi Kanzaki, and Tomofumi Yamamoto, compile all the latest research on PWRs into this comprehensive reference.

Beginning with an analysis of the history of PWR development, the reader is guided through optimum design processes for PWRs, considering safety throughout. Thermal-hydraulic aspects within the PWR system, as well as inside the reactor core, are also discussed.

This book explores the advancement and improvement of fuel and includes analysis codes for the design and safety of PWRs. The future prospects for the next generation of PWR and small modular reactors are discussed, thus providing the reader with a basis for further research of their own.

As with the other volumes in this series, this book will be an invaluable resource for nuclear and thermal engineers and researchers.

Cover image
Title page
Table of Contents
Copyright
List of contributors
About the editors and authors
About the editors
About the authors
Preface of JSME Series in Thermal and Nuclear Power Generation
Preface
Editorial secretariat
Cooperation
Abbreviations
1. History of pressurized water reactor development in Japan
Abstract
Chapter outline
1.1 Introduction
1.2 Outline of pressurized water reactor
1.3 Brief history of nuclear development
1.4 Development of pressurized water reactor
1.5 Nuclear safety and regulations
References
Further reading
2. Features of a PWR plant
Abstract
2.1. Introduction
Further reading
2.2. Safety design philosophy
2.2.1 Outline
2.2.2 Consideration of external events
2.2.3 Consideration on internal events
2.2.4 Safety facilities for design basis events
2.2.5 Safety facilities for severe accidents
2.2.6 Specialized safety facilities
2.2.7 Radiation protection
2.3. Plant layout
2.3.1 Outline
2.3.2 Plot plan
2.3.3 Layout of systems and components
2.3.4 Design considerations for plant layout
Further reading
2.4. Reactor and core
2.4.1 Outline
2.4.2 Fuel rod and fuel assembly
2.4.3 Reactor and core
2.5. Reactor coolant system
2.5.1 Outline
2.5.2 Reactor pressure vessel
2.5.3 Reactor internals
2.5.4 Steam generator
2.5.5 Reactor coolant pump
2.5.6 Pressurizer
2.5.7 Main coolant pipe
2.6. Power conversion system
2.6.1 Outline
2.6.2 Major systems, components and heat cycle
2.6.3 Steam turbine for PWR
2.6.4 Main steam system
2.6.5 Condensate and feedwater system
2.6.6 Auxiliary feedwater system
2.6.7 Circulating water system
2.6.8 Generator
2.7. Engineered safety features
2.7.1 Outline
2.7.2 Emergency core cooling system
2.7.3 Reactor containment
2.7.4 Containment spray system
2.7.5 Emergency exhaust system
2.8. Safety features for design extension conditions
2.8.1 Outline
2.8.2 Significant core damage prevention countermeasure
2.8.3 CV damage prevention countermeasure
2.8.4 Specialized safety facilities against severe accidents
2.9. Reactor auxiliary systems
2.9.1 Outline
2.9.2 Chemical and volume control system
2.9.3 Residual heat removal system
2.9.4 Component cooling water system
2.9.5 Sea water system
2.9.6 Spent fuel pit cooling and purification system
2.9.7 Fuel storage and handling system
2.9.8 Heating, ventilating, and air conditioning systems
2.10. Radioactive waste management systems
2.10.1 Liquid waste processing system
2.10.2 Gaseous waste processing system
2.10.3 Solid waste processing system
2.11. Instrumentation and control (I&C) system
2.11.1 Outline
2.11.2 Nuclear instrumentation system
2.11.3 Safety protection system
2.11.4 Reactor control system
2.11.5 Control rod drive system
2.11.6 Radiation monitoring system
2.11.7 Main control panel
2.11.8 Instrumentation and control system responding to accident events
2.12. Electrical systems
2.12.1 Outline
2.12.2 Major transformers and power transmission system
2.12.3 Onsite electrical power systems
2.12.4 Electrical power systems for severe accidents
3. Plant operation and maintenance
Abstract
Chapter outline
3.1 Introduction
3.2 Plant operation
3.3 Plant maintenance
3.4 Plant life management
Further reading
4. Safety evaluation
Abstract
Chapter outline
4.1 Introduction
4.2 Anticipated operational occurrence
4.3 Design basis accidents
4.4 Design extension condition
4.5 Measures against intentional aircraft crashes, etc
4.6 Probabilistic risk assessment and safety margin
4.7 Continuous safety improvement
References
Further reading
5. Advanced PWRs
Abstract
Chapter outline
5.1 Introduction
5.2 Advanced PWRs
5.3 US-APWR
5.4 EU-APWR
5.5 SRZ-1200
5.6 Small LWR
References
6. Technology developments and innovations
Abstract
6.1. Introduction
6.2. Accident tolerant fuel
6.2.1 Overview
6.2.2 Cr-coated cladding tube
6.2.3 SiC cladding
6.2.4 Summary
6.3. Seismic design methodology of primary components
6.3.1 Introduction
6.3.2 Seismic resistance improvement for replacement RI
6.3.3 Seismic evaluation sophistication for steam generator
6.4. Safety evaluation methodology
6.4.1 Introduction
6.4.2 Advancement of nuclear design technology
6.4.3 Advancement of thermal-hydraulic design technology
6.4.4 Advancement of the non–LOCA evaluation technology
6.4.5 Advancement of the LOCA evaluation technology
6.5. Robotics
6.5.1 Requirements for nuclear power plant maintenance robots
6.5.2 Technologies that materialize nuclear power plant maintenance robots (articulated manipulator)
6.5.3 Application of robots to reactor vessel maintenance
6.5.4 Application of robots to steam generator maintenance
6.5.5 Development of nuclear disaster response robots
6.5.6 Conclusion
Further reading
Index