Thermal Analysis of Pressurized Water Reactors


Book Description

The basic objective of this book is to present the principles underlying the thermal and hydraulic design of pressurized water reactors. In addition, the empirical data, engineering properties, and computer techniques required for design, but not available in conventional handbooks, are presented or referenced. Because of the many advances and changes that have occurred since the second edition, extensive improvements in both understanding the phenomena involved and in calculational techniques are reflected in the substantial additions to this third edition. Also, an additional chapter has been added to accommodate the many developments in the area of safety analysis.










STDY-3


Book Description
















The Thermal-hydraulics of a Boiling Water Nuclear Reactor


Book Description

This edition of the classic monograph gives a comprehensive overview of the thermal-hydraulic technology underlying the design, operation, and safety assessment of boiling water reactors. In addition, new material on pressure suppression containment technology is presented.




Pressurized Water Reactors


Book Description

Pressurized Water Reactors, Volume Three in the JSME Series on Thermal and Nuclear Power Generation, compiles the latest research on Pressurized Water Reactors (PWRs) into a very comprehensive reference, beginning with its history. The reader is then guided through optimum design processes for PWRs, considering safety throughout. The authors then discuss thermal-hydraulic aspects within the PWR system and inside the reactor core, making this a valuable resource for nuclear and thermal engineers and researchers. Combining their wealth of experience, the book presents in-depth knowledge on the advancement and improvement of fuel rods that is gleaned from decades of experience and lessons learned. The inclusion of analysis codes for the design and safety elements ensure makes this a unique reference which will provide the reader with a solid understanding which they can transfer to their own professional and research settings. Future prospects for next generation PWR and Small Modular Reactors are also discussed, giving the reader a basis for further research of their own. - 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