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.
Edited by:
Jovica Riznic (Technical Specialist Canadian Nuclear Safety Commission (CNSC) Canada)
Imprint: Woodhead Publishing
Country of Publication: United States
Edition: 2nd edition
Dimensions:
Height: 276mm,
Width: 216mm,
Weight: 1.000kg
ISBN: 9780443290305
ISBN 10: 044329030X
Pages: 804
Publication Date: 04 November 2025
Audience:
Professional and scholarly
,
Undergraduate
Format: Hardback
Publisher's Status: Active
Part One: Design and Manufacturing 1. Introduction to steam generators- from Heron of Alexandria to nucleasr power plants: Brief history and literature survey 2. Nuclear steam generator design 3. Nuclear steam generator manufacturing 4. Thermal hydraulics, circulation and steam-water separation in nuclear steam generators Part Two: Operation and Maintenance 5. Steam-Water cycle chemistry relevant to nuclear steam generators 6. Corrosion Problems Affecting Steam Generator Tubes in Commercial Water Cooled Nuclear Power Plants 7. Environmental degradation of materials in nuclear steam generators 8. Corrosion product transport and fouling in nuclear steam generators 9. Corrosion hideout and hideout return in nuclear steam generators 10. Deposit management in nuclear steam generators: Chemical cleaning and decontamination 11. Thermal Performance Degradation 12. Flow induced vibrations in nuclear steam generators 13. Structural integrity of nuclear steam generators 14. Nuclear steam generator inspection and testing 15. Nuclear steam generator tube inspection tools 16. Nuclear steam generator fitness-for-service assessment 17. Regulatory requirements and consideration for nuclear steam generators 18. Fitness for service Guidelines 19. VVER Steam Generators 20. VVER Steam Generators - Modelling & Simulations 21. Leakage through cracked tubes 22. Secondary side components - operating experience 23. Full Bundle Probabilistic Analysis, for the Evaluation of Steam Generator Tube Integrity 24. Maintenance of steam generators at nuclear power plants/ Vendors perspective on SG Inspections 25. Operation and maintenance of nuclear steam generators- Utility Perspective 26. Nuclear steam generator tube manufacturing 27. Probabilistic Models for Steam generator Life Cycle Predictions. Probabilistic Modelling Approaches for Flaw Growth Rate Estimation in a Multi-Component System. 28. Replacement Steam Generators 29. Fretting Fatugue in Steam Generators 30. Modeling to two-phase flow fluidelastic instabilities 31. Degradations by foreign objects 32. Transient behaviors of steam generators Part Three: Emerging Topics 33. Printed Circuit Steam Generators 34. Helical Coil steam generators 35. Instrumentation & Control and Artificial intelligence 36. Steam Generators for Fusion Reactors 37. Steam Generators for Fast Breeder Reactors 38. Steam Generators for High Temperature reactors 39. Nuclear steam generators: Conclusions
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.