Boiling Water Reactors

1st Edition - January 26, 2023
Editors: Koji Nishida, Shinichi Morooka, Michitsugu Mori, Yasuo Koizumi
Language: English
Paperback ISBN:
9 7 8 - 0 - 1 2 - 8 2 1 3 6 1 - 2
eBook ISBN:
9 7 8 - 0 - 1 2 - 8 2 1 3 6 8 - 1

Boiling Water Reactors, Volume Four in the JSME Series on Thermal and Nuclear Power Generation compiles the latest research in this very comprehensive reference that begins wi… Read more

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Boiling Water Reactors, Volume Four in the JSME Series on Thermal and Nuclear Power Generation compiles the latest research in this very comprehensive reference that begins with an analysis of the history of BWR development and then moves through BWR plant design and innovations. The reader is guided through considerations for all BWR plant features and systems, including reactor internals, safety systems and plant instrumentation and control. Thermal-hydraulic aspects within a BWR core are analyzed alongside fuel analysis before comparisons of the latest BWR plant life management and maintenance technologies to promote safety and radiation protection practices are covered.

The book's authors combine their in-depth knowledge and depth of experience in the field to analyze innovations and Next Generation BWRs, considering prospects for a variety of different BWRs, such as High-Conversion-BWRs, TRU-Burner Reactors and Economic Simplified BWRs.

Cover image
Title page
Table of Contents
Copyright
Contributors
About the Authors
Preface of JSME series in Thermal and Nuclear Power Generation
Preface
Editing working group for volume 4: Boiling water reactors
Abbreviations
1: History of BWR development
Abstract
1.1: Nuclear energy development in Japan
1.2: Establishment and realization of BWR technologies
1.3: Improvement and standardization program in Japan
1.4: Improvement of system and construction [1–7]
1.5: Construction experience and operation performance [1–8]
2: Features of BWR plant
Abstract
2.1: Introduction
2.2: Reactor
2.3: Reactor coolant system and connected systems
2.4: Engineered safety features
2.5: Instrumentation and controls
2.6: Electric power
2.7: Auxiliary system
2.8: Steam and power conversion systems
3: Nuclear reactor dynamics and thermal hydraulics of reactor core and fuel assembly
Abstract
3.1: Reactor internals and coolant flow paths in a reactor pressure vessel
3.2: Advances of reactor core and fuel assembly
3.2.1: High burnup fuel design
3.2.2: MOX fuel design
3.2.3: Thermal-hydraulic design
3.2.4: Enhancement of critical power
3.2.5: Countermeasures and cause of fuel rod failure
3.2.6: Proving test on the thermal-hydraulic performance of BWR fuel assembly
3.3: Advances in reactor core and fuel assembly analysis
3.3.1: Nuclear analysis in BWRs
3.3.2: Thermal-hydraulics system analysis codes and subchannel analysis codes
3.4: Advances in containment vessel design
3.5: Advances in safety analysis code and safety systems
4: Fukushima Daiichi nuclear power plant accident and analysis evaluation
Abstract
4.1: Outline of accident
4.2: Event progress and analysis evaluation at Unit 1
4.3: Event progress and analysis evaluation at Unit 2
4.4: Event progress and analysis evaluation at Unit 3
4.5: Hydrogen explosion at Unit 4
4.6: Avoiding severe accidents at Fukushima Daini NPS
4.7: Lessons learned from Fukushima Daiichi accident
4.8: New nuclear regulatory requirements in Japan
4.9: Example of compliance with new regulatory standards for PWRs that can be used as a reference for BWRs
4.10: BWR NPS to be reviewed for new requirements or restarting
4.11: Activities toward decommissioning Fukushima Daiichi
4.12: Important lessons learned from Fukushima Daiichi NPS accident
References
5: BWR innovations
Abstract
5.1: Trans-uranic (TRU) burner reactor and reduced-moderation water reactor
5.1.1: TRU burner reactor
5.1.2: Reduced-moderation light water reactor
5.2: Design innovation of BWR and high-pressure BWR
5.3: Power uprate in BWR
5.4: Post-BT standard for BWR power plant
5.5: Core catcher
5.6: Steam injector
5.7: Built in upper internal control rod drives (CRDs) for ABWR-III
Index

Koji Nishida

Nishida, Koji received a Doctor of Engineering degree in 1987 from Kobe University for his study on convective film boiling heat transfer. He entered Hitachi Research Laboratory where he started researching thermal hydraulics of boiling water reactors (BWRs). He was engaged in developing high burn-up fuel bundles and high performance next generation BWRs including the SMR, Small Modular Reactor. After the Fukushima Daiichi Nuclear Power Station accident in 2011, he was engaged in analyzing the accident progression. He moved to the Institute of Nuclear Safety System in 2017. At present, he is doing research on severe accidents and safety systems for pressured water reactors.

Affiliations and expertise

Institute of Nuclear Safety System, Mihama, Fukui, Japan

Shinichi Morooka

Morooka, Shinichi is an emeritus professor of Waseda University. He graduated from the Doctor course of Mechanical Engineering at Waseda University in 1977. He received Dr. Eng. degree from Waseda University in 1980. His research field is Thermal-hydraulics of Nuclear Power Plant. He worked at Toshiba Corporation in the thermal-hydraulics R&D Center of nuclear power plants for about 30 years. He has a great deal of experience in developing components for actual nuclear power plants. He came back to Waseda University as a professor in 2010. He is an emeritus professor of Waseda University. Now, he optimizes the heat transfer performance for Light Water Reactor components using Computed Fluid Dynamics code and experimental technologies. Target Components are Nuclear Fuel, Separator system, Steam Generator, so on. He constructs flow mechanism, develops an original simulation code based on flow mechanisms and predicts the heat transfer performance of fuel assembly.

Affiliations and expertise

Emeritus Professor of Waseda University, Shinjuku, Tokyo, Japan

Michitsugu Mori

Mori, Michitsugu is currently an invited guest professor of the Graduate School of Engineering, Hokkaido University and a guest researcher of Japan Atomic Energy Agency (JAEA). He researched the quenching cooling process of a fuel rod during reactivity-initiated accidents at Department of Nuclear Engineering, Graduate School of Engineering, Tohoku University, Japan and was awarded 1981 with Dr. of Eng. He researched a modular gas-cooled reactor (MGR) Brayton cycle and components at the Department of Nuclear Science & Engineering of Massachusetts Institute of Technology (MIT), USA from 1987 to 1989. He joined the R & D Center of Tokyo Electric Power Company (TEPCO), and then researched the LWR thermal-hydraulics and advanced measurement technologies including next generation reactors. He became a full professor at Hokkaido University in 2012 and performed the experiments and simulations on the nuclear system safety, e. g., reactor core injection system, plant transient and debris behaviors, and next generation reactors. He was the president of JSMF, JSME and AESJ Board of Directors, the vice-presidents of HTSJ and AESJ, and currently is the fellows of JSME and AESJ, and the honorary members of JSME and HTSJ.

Affiliations and expertise

Invited Guest Professor of Graduate School of Engineering, Hokkaido University, Sapporo, Hokkaido, Japan, and Guest Researcher of JAEA, Tokai, Ibaraki, Japan

Yasuo Koizumi

Koizumi, Yasuo is a research promotor and an invited researcher at the University of Electro-Communications at present. He had been an invited researcher of the Japan Atomic Energy Agency for five years before now. He received his PhD degree from the University of Tokyo in 1977. He started his research career at the Japan Atomic Energy Research Institute in 1977 as a research engineer for nuclear reactor safety. He stayed at the Idaho National Engineering Laboratory from 1981 through 1983. He moved to the Department of Mechanical Engineering of Kogakuin University in 1989. Then, he moved to the Department of Functional Machinery and Mechanics of Shinshu University in 2008. He retired as professor in 2014 and he had been in the Japan Atomic Energy Agency since then. His research is focused in the areas of pool and flow boiling, critical heat flux, condensation heat transfer, and two-phase flow. He is also interested in heat transfer and fluid flow on the microscale. Since his research field is closely related to energy systems, he has great interest in thermal and nuclear power stations and energy supply in society.

Affiliations and expertise

The University of Electro-Communications, Chofu, Tokyo, Japan