Steam Generators for Nuclear Power Plants, Second Edition continues its legacy of examining all phases of the lifecycle of nuclear steam generators (NSGs), components which are essential for the efficient and safe operation of nuclear reactors. This book is broken into three sections: design and manufacturing, operation and maintenance, and emerging topics. This revised edition includes new chapters on fitness for service guidelines; VVER steam generators; leakage through cracked tubes; secondary side components; full bundle probabilistic analysis; maintenance of steam generators; probabilistic models for steam generator life cycle predictions; steam generators for small modular and advanced nuclear reactors, and much more.
This timely revision serves as a resource for professionals involved in all phases of the NSG lifecycle, from design, manufacturing, operation and maintenance, to fitness-for-service and long-term operation. It is also intended as a valuable resource for students and researchers interested in a range of topics relating to NSG lifecycle management.
- Presents state-of-the-art steam generators for current and advanced nuclear power plants and small modular and micro reactors
- Contains comprehensive coverage of all phases of the nuclear steam generator lifecycle, including design, manufacturing, operation, maintenance, fitness-for-service, and long-term operation
- Addresses new concepts of steam generators like helical coil and printed circuit steam generators
Jovica R Riznic, PhD., P.Eng., FASME, is a Technical Specialist with the Canadian Nuclear Safety Commission (CNSC), working on regulatory analysis and assessment of technical issues with operating nuclear power plants (NPP). He served CNSC on various position, including nuclear safety analysis and managing the CNSC Research and Support Program. He served as an adjunct professor/thesis advisor at the University of Waterloo, Mc Master, and Purdue Universities and currently is on faculty at Algonquin College in Ottawa in the School of Business and the Centre for Continuing and Online. He conducted research at Argonne National Laboratory, Purdue University and University of Wisconsin-Milwaukee in the areas of heat and mass transfer, nuclear reactor thermal hydraulics, multi-phase thermo-fluid systems, nuclear reactor safety and reliability, and engineering management. He is currently coordinating a team providing Canadian contribution to a number of international research projects with US Nuclear Regulatory Commission (NRC), Nuclear Energy Agency of the Organization for Economic Cooperation and Development (OECD NEA) and International Atomic Energy Agency (IAEA) to address issues of material degradation and safe operation of piping components and steam generators of CANDU and Light Water Reactors. Also, he leads a team of researchers working with Purdue University on refining the CANTIA methodology for steam generator tube integrity, leakage inspection and probabilistic assessment. Currently he is the Founding Editor of the ASME Nuclear Engineering and Technology for 21st Century Concise Monographs Series, Associate Editor of the ASME Nuclear Engineering and Radiation Science Journal and the on the Editorial Board of the Nuclear Engineering and Design Journal.
