Description
Pressurized Water Reactors
JSME Series in Thermal and Nuclear Power Generation Series
Coordinators: Kanzaki Yurugi, Mimaki Hidehito, Yamamoto Tomofumi
Language: EnglishSubjects for Pressurized Water Reactors:
Keywords
Nuclear energy; nuclear reactors; pressurized water reactors; PWRs; nuclear power plants; nuclear systems; power generation; APWR; PWR systems; primary loop; reactor vessels; coolant pumps; generators; turbines; boron Rankine cycles; thermal regeneration systems; nuclear safety; high-pressure injection; Nuclear I& C; nuclear plant shutdown; nuclear thermal-hydraulics; reactor core; fuel assembly; cooling water systems; fuel analysis; plant life analysis; plant maintenance; next generation reactors
400 p. · 15x22.8 cm · Paperback
Description
/li>Contents
/li>Biography
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Pressurized Water Reactors is the sixth volume in the JSME Series on Thermal and Nuclear Power Generation. In this volume, series editor Yasuo Koizumi and his volume editors, Hidehito Mimaki, Yurugi Kanzaki, and Tomofumi Yamamoto, compile all the latest research on PWRs into this comprehensive reference.
Beginning with an analysis of the history of PWR development, the reader is guided through optimum design processes for PWRs, considering safety throughout. Thermal-hydraulic aspects within the PWR system, as well as inside the reactor core, are also discussed.
This book explores the advancement and improvement of fuel and includes analysis codes for the design and safety of PWRs. The future prospects for the next generation of PWR and small modular reactors are discussed, thus providing the reader with a basis for further research of their own.
As with the other volumes in this series, this book will be an invaluable resource for nuclear and thermal engineers and researchers.
2. PWR plant designs
3. Nuclear thermal-hydraulics of reactor core and fuel assembly
4. Plant Life Management and Maintenance Technologies
5. PWR Innovations
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.
Contains contributions from 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 analysis codes, such as RELAP5, for the design and safety improvement of pressurized water reactors (PWRs)
Presents history, examples, and case studies from Japan and other key regions, such as the United States and Europe