Sodium-cooled Fast Reactors
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Sodium-cooled Fast Reactors is the third volume in the JSME Series on Thermal and Nuclear Power Generation, which presents a comprehensive view of the latest research and activities from around the globe. Volume Editors Masaki Morishita and Hiroyuki Ohshima, along with their team of expert contributors, combine their knowledge and experience to provide a solid understanding of the history of SFRs and work carried out in Japan to date. This book uniquely includes case studies from these global regions to highlight SFR uses, benefits and challenges, focusing on their safety, design, operation, and maintenance. Unique to this publication, the JSME cover key technological advances which will shape power generation of the future, including developments in the use of AI for design. Drawing on their unique experience, the authors pass on lessons learned and best practices to support professionals and researchers in their development and design of this advanced reactor type.
Key Features
- Written by the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers and draws upon their combined wealth of knowledge and experience
- Includes real examples and case studies mainly from Japan to provide a deeper learning opportunity with practical benefits
- Considers the societal impact and sustainability concerns and goals throughout the discussion
- Includes safety factors and considerations, as well as unique results from performance testing of SFR systems
Readership
Nuclear engineering and researchers focusing on SFR(s); SFR plant designers and operators; regulators; post graduate students of nuclear engineering; thermal energy engineers and researchers; national labs; government officials and agencies in power and energy policy and regulations
Table of Contents
1. Introduction
1.1 Sodium-cooled Fast Reactor
1.2 Functions of SFR Cycle and Technology
1.3 Needs for SFRs
1.4 FBR Development Policy
1.5 History of SFR Development in Japan
1.6 Overview of this Volume2. Experimental Reactor Joyo
2.1 Introduction
2.2 Operation and Maintenance Experience
2.3 Irradiation Test Experience and Future Plan3. Prototype Reactor Monju
3.1 Design Features
3.2 R&D Activities for Monju Design
3.3 Operation and Maintenance
3.4 R&D Achievements in Monju4. Demonstration Plant Design Study
4.1 DFBR; demonstration reactor project lead by the utilities
4.2 JSFR Developed in the FaCT Project
4.3 Safety improvement of JSFR
4.4 Pool-type SFR5. Key Technologies for Future SFRs
5.1 Safety
5.2 Sodium Components Development
5.3 Reactor Core Physics
5.4 Fuel and Materials
5.5 Thermal Hydraulics
5.6 High Temperature Structural Materials and Structural Design
5.7 Seismic Design
5.8 Operation and Maintenance
5.9 Fuel Cycle Related Studies
5.10 ARKADIA ‒Advanced Reactor Knowledge- and AI-aided Design Integration
Product details
- No. of pages: 400
- Language: English
- Copyright: © Academic Press 2022
- Published: July 15, 2022
- Imprint: Academic Press
- Paperback ISBN: 9780128240762
About the Series Editor
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
About the Editors
Masaki Morishita
Dr. Masaki Morishita is a senior consulting engineer with Japan Atomic Energy Agency, and has almost 40 years’ experience in R&D related to high temperature structural design and seismic design of Sodium Fast Reactors mechanical components.
He also has been active in the nuclear codes and standards development activities both in JSME and ASME for more than 20 years. He is a past Chair of JSME Main Committee on Power Generation Facility Codes, and is also a past chair of Subgroup High Temperature Reactors of ASME Boiler and Pressure Vessel Code Section III.
He is a fellow of both JSME and ASME.
Affiliations and Expertise
Fast Reactor Cycle System Research and Development Center, Sector of Fast Reactor and Advanced Reactor Research and Development, Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Hiroyuki Ohshima
Mr. Hiroyuki Ohshima is an executive board director of Japan Atomic Energy Agency. As a researcher, he has more than 30 years of experience in research and development related to thermal-hydraulic issues and safety specific to sodium-cooled fast reactors after graduating from the University of Tokyo Graduate School. He also has been committed to the JSME and AESJ activities; he is a past chair of the planning committee of Power and Energy Systems Division of JSME and currently he is the chair of subcommittee on thermal hydraulics of AESJ. He is a fellow of JSME.
Affiliations and Expertise
Executive Board Director, Director General of Research and Development Sector for Fast Reactor and Advanced Reactor, Japan Atomic Energy Agency, Tokai, Ibaraki, Japan