Steam Generators for Nuclear Power Plants

2. Auflage 2025
ISBN: 978-0-443-29030-5
Verlag: Elsevier Science

Buch, Englisch, 777 Seiten, Format (B × H): 191 mm x 235 mm

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.

Autoren/Hrsg.

Riznic, Jovica

Fachgebiete

• Technische Wissenschaften Maschinenbau | Werkstoffkunde Maschinenbau Dampfmaschinen, Dampfturbinen, Stirlingmotoren
• Technische Wissenschaften Energietechnik | Elektrotechnik Atomenergietechnik

Inhaltsverzeichnis

Preface

Part One: Design and Manufacturing
1. Introduction to steam generators- from Heron of Alexandria to nuclear 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

5. Replacement Steam Generators

Part Two: Operation and Maintenance
6. Steam-Water cycle chemistry relevant to nuclear steam generators

7. Corrosion and Other Degradation in Commercial PWR / PHWR Steam Generator Tubes

8. Environmental degradation of materials in nuclear steam generators

9. Corrosion product transport and fouling in nuclear steam generators

10. Corrosion hideout and hideout return in nuclear steam generators

11. Steam Generator Deposit Accumulation and Removal: Chemical and Mechanical Methods

12. Thermal Performance Degradation: Heat-Transfer Fouling and Other Causes

13. Flow induced vibrations in nuclear steam generators

14. The Acoustic Resonance Phenomenon

15. Nuclear steam generator inspection and testing

16. Nuclear steam generator tube inspection tools

17. Nuclear steam generator fitness-for-service assessment

18. Regulatory requirements and consideration for nuclear steam generators

19. Fitness for service Guidelines

20. VVER Steam Generators

21. VVER Steam Generators - Modelling & Simulations

22. Horizontal Steam Generators - Safety Studies

23. Leakage through cracked tubes

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. Fretting Fatigue and Wear in Steam Generators

27. MODELS FOR TWO-PHASE FLOW INDUCED FLUID-ELASTIC INSTABILITY

Part Three: Emerging Topics
28. Printed Circuit Steam Generators

29. Helical Coil steam generators

30. Steam Generators for Small Modular Reactors

31. System and Computational Fluid Dynamic Modeling to Support High Temperature Steam Generator Design

32. Machine Learning Applications in Nuclear Steam Generators

Appendices

Über Autor(innen)

Riznic, Jovica
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.