High-Temperature Gas Reactors is the fifth volume in the JSME Series on Thermal and Nuclear Power Generation. Series Editor Yasuo Koizumi and his Volume editors Tetsuaki Takeda and Yoshiyuki Inagaki present the latest research on High-Temperature Gas Reactor (HTGR) development and utilization, beginning with an analysis of the history of HTGRs. A detailed analysis of HTGR design features, including reactor core design, cooling tower design, pressure vessel design, I&C factors and safety design, provides readers with a solid understanding of how to develop efficient and safe HTGR within a nuclear power plant.The authors combine their knowledge to present a guide on the safety of HTGRs throughout the entire reactor system, drawing on their unique experience to pass on lessons learned and best practices to support professionals and researchers in their design and operation of these advanced reactor types. Case studies of critical testing carried out by the authors provide the reader with firsthand information on how to conduct tests safely and effectively and an understanding of which responses are required in unexpected incidents to achieve their research objectives. An analysis of technologies and systems in development and testing stages offer the reader a look to the future of HTGRs and help to direct and inform their further research in heat transfer, fluid-dynamics, fuel options and advanced reactor facility selection.This volume is of interest for nuclear and thermal energy engineers and researchers focusing on HTGRs, HTGR plant designers and operators, regulators, post graduate students of nuclear engineering, national labs, government officials and agencies in power and energy policy and regulations.
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Table of Contents
1. Overview of high temperature gas-cooled reactor2. Design of High Temperature Engineering Test Reactor (HTTR)
3. R&D on components
4. Operation of HTTR
5. R&D on commercial high temperature gas-cooled reactor
Authors
Tetsuaki Takeda Graduate Faculty of Interdisciplinary Research, Research Faculty of Engineering, Department of Mechanical Engineering,University of Yamanashi, Yamanashi, Japan. Tetsuaki Takeda has been a professor of Graduate Faculty of Interdisciplinary Research, Research Faculty of Engineering, Department of Mechanical Engineering, University of Yamanashi since 2008. He was graduated from Kobe University, majored in nuclear engineering in 1982, and received his doctoral degree at The University of Tokyo in 1997. He stayed at University of California Los Angeles (UCLA) as a visiting researcher from 1993 to 1994. He has transferred his field of academic goal from Japan Atomic Energy Agency to University of Yamanashi in 2008. His research field is the thermo-hydraulics related in not only nuclear energy but also renewable energy. During his service in JAEA, he performed the experiments and analyses of the safety studies regarding the VHTR systems and the nuclear hydrogen production systems developments. Afterward, he has also performed experiment and analysis regarding a ground source heat pump system, solar thermal collector system, heat utilization system using thermoelectric devices, and so on. He served Chairman of Power and Energy Systems Division of Japan Society of Mechanical Engineers (JSME). Yoshiyuki Inagaki Department of Hydrogen and Heat Application Research and Development, HTGR Research and Development Center, Japan Atomic Energy Agency, Ibaraki, Japan. Yoshiyuki Inagaki is Researcher of Department of Hydrogen and Heat Application Research and Development, HTGR Research and Development Center, Oarai Research and Development Institute, Sector of Fast Reactor and Advanced Reactor Research and Development in JAEA. He received his PhD degree from Kyushu University in 1996. He started his research career at JAERI in 1981 for the HTGR technology such as reactor internals and high temperature components. He then worked in Juelich Research Center in Germany from 1994 to 1995 for a hydrogen production process. He also researched HTGR heat application systems such as hydrogen production and nuclear steelmaking systems and the system integration technology for safe connection between a reactor and a hydrogen production system.
