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. Written by experts from the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers - Includes real examples and case studies from Japan, the US and Europe to provide a deeper learning opportunity with practical benefits - Considers societal impacts and sustainability concerns and goals throughout the discussion - Explores BWR plant design, thermal-hydraulic aspects, the reactor core and plant life management and maintenance in one complete resource Guides the reader through BWR development, operation, thermal-hydraulics and fuel assembly, including case studies and analysis code throughout Boiling Water Reactors is the fourth volume in the JSME Series on Thermal and Nuclear Power Generation . Series Editor Yasuo Koizumi and his Volume editors Koji Nishida, Okamoto Koji and Akira Onuki compile the latest research on Boiling Water Reactors (BWRs) in this very comprehensive reference, beginning with an analysis of the history of BWR development and moving through BWR plant design and innovations. The reader is guided through their consideration of 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 comparison of the latest BWR plant life management and maintenance technologies to promote safety and radiation protection practices. The authors combine their in-depth knowledge and depth of experience of 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. This comprehensive resource on BWRs equips the reader with a solid understanding of the latest technologies to inform their further research and enable them to safely design a BWR power plant with optimum internal systems, and operate safely at all stages of the process. 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. 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. 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