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.

• PrefacePart One: Design and Manufacturing1. Introduction to steam generators- from Heron of Alexandria to nuclear power plants: Brief history and literature survey2. Nuclear steam generator design3. Nuclear steam generator manufacturing4. Thermal hydraulics, circulation and steam-water separation in nuclear steam generators5. Replacement Steam GeneratorsPart Two: Operation and Maintenance6. Steam-Water cycle chemistry relevant to nuclear steam generators7. Corrosion and Other Degradation in Commercial PWR / PHWR Steam Generator Tubes8. Environmental degradation of materials in nuclear steam generators9. Corrosion product transport and fouling in nuclear steam generators10. Corrosion hideout and hideout return in nuclear steam generators11. Steam Generator Deposit Accumulation and Removal: Chemical and Mechanical Methods12. Thermal Performance Degradation: Heat-Transfer Fouling and Other Causes13. Flow induced vibrations in nuclear steam generators14. The Acoustic Resonance Phenomenon15. Nuclear steam generator inspection and testing16. Nuclear steam generator tube inspection tools17. Nuclear steam generator fitness-for-service assessment18. Regulatory requirements and consideration for nuclear steam generators19. Fitness for service Guidelines20. VVER Steam Generators21. VVER Steam Generators - Modelling & Simulations22. Horizontal Steam Generators – Safety Studies23. Leakage through cracked tubes24. Maintenance of steam generators at nuclear power plants/ Vendors perspective on SG Inspections25. Operation and maintenance of nuclear steam generators- Utility Perspective26. Fretting Fatigue and Wear in Steam Generators27. MODELS FOR TWO-PHASE FLOW INDUCED FLUID-ELASTIC INSTABILITYPart Three: Emerging Topics28. Printed Circuit Steam Generators29. Helical Coil steam generators30. Steam Generators for Small Modular Reactors31. System and Computational Fluid Dynamic Modeling to Support High Temperature Steam Generator Design32. Machine Learning Applications in Nuclear Steam GeneratorsAppendices