Sodium-cooled Fast Reactors

Erscheinungsjahr 2022
ISBN: 978-0-12-824076-2
Verlag: William Andrew Publishing

Buch, Englisch, 662 Seiten, Format (B × H): 152 mm x 229 mm, Gewicht: 1040 g

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.

Zielgruppe

<p>Nuclear engineering and researchers focusing on FBRs; FBR 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</p>

Autoren/Hrsg.

Morishita, Masaki

Ohshima, Hiroyuki

Weitere Mitwirkende

Koizumi, Yasuo

Fachgebiete

• Wirtschaftswissenschaften Betriebswirtschaft Bereichsspezifisches Management Arbeitsplatz, Arbeitsschutz, Gefahrstoffschutz
• Technische Wissenschaften Energietechnik | Elektrotechnik Atomenergietechnik
• Wirtschaftswissenschaften Wirtschaftssektoren & Branchen Energie- & Versorgungswirtschaft Kernenergieindustrie

Inhaltsverzeichnis

1. Introduction 2. Experimental Reactor Joyo 3. Prototype Reactor Monju 4. Demonstration Plant Design Study 5. Key Technologies for Future SFRs

Über Autor(innen)

Ohshima, Hiroyuki
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.

Koizumi, Yasuo
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.

Morishita, Masaki
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.