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Steam Generators for Nuclear Power Plants [Kõva köide]

Edited by (Technical Specialist, Canadian Nuclear Safety Commission (CNSC), Canada)
  • Formaat: Hardback, 578 pages, kõrgus x laius: 229x152 mm, kaal: 770 g
  • Ilmumisaeg: 25-May-2017
  • Kirjastus: Woodhead Publishing Ltd
  • ISBN-10: 0081008945
  • ISBN-13: 9780081008942
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Steam Generators for Nuclear Power PlantsSuurem pilt
  • Formaat: Hardback, 578 pages, kõrgus x laius: 229x152 mm, kaal: 770 g
  • Ilmumisaeg: 25-May-2017
  • Kirjastus: Woodhead Publishing Ltd
  • ISBN-10: 0081008945
  • ISBN-13: 9780081008942
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Märksõnad:

Steam generators for nuclear power plants examines all phases of the life cycle of nuclear steam generators (NSGs), components which are essential for the efficient and safe operation of light water reactors (LWRs). Coverage spans the design, manufacturing, operation and maintenance, fitness-for-service and long term operation of these key reactor parts.

Part 1 opens with a chapter by the editor that provides fundamental background on NSG engineering and operational experiences. The following chapters then review the different NSG concepts, describe NSG design and manufacturing and consider the particularities of SGs for VVER reactors. Part 2 then focuses on NSG operation and maintenance, starting with an overview of the activities required to support reliable and safe operation. The discussion then moves on to tubing vibration, followed by the water and steam cycle chemistry issues relevant to the NSG lifecycle. Finally a number of chapters focus on the key issue of corrosion in NSGs from different angles.

This book serves as a timely resource for professionals involved in all phases of the NSG life cycle, 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 related to NSG life cycle management. The book does not relate any specific vendor-based technologies but rather provides a broad generic technology overview across PWR, VVER and PHWR nuclear power plant technologies.

  • Fulfills the need for a book specifically on steam generators for nuclear power plants
  • Comprehensive coverage of all phases of the nuclear steam generator life cycle, from design, manufacturing, operation and maintenance, to fitness-for-service and long term operation in one convenient volume.
  • Contributions from key manufacturers, as well as research institutes and universities

Muu info

Examines all phases of the lifecycle of nuclear steam generators (NSGs) for the efficient and safe operation of light water reactors (LWRs)
List of contributors
xi
Preface xiii
Part One Design and manufacturing
1(124)
1 Introduction to steam generators---from Heron of Alexandria to nuclear power plants: Brief history and literature survey
3(32)
J. Riznic
1.1 Introduction
3(2)
1.2 Brief history of steam generation
5(6)
1.3 Splitting of the atom and emergence of nuclear power: Atoms join water and steam
11(5)
1.4 Unique features of different steam generators
16(11)
1.5 Steam generators literature survey
27(8)
References
31(2)
Further reading
33(2)
2 Nuclear steam generator design
35(20)
J.C. Smith
2.1 Introduction
35(1)
2.2 Specifications
35(1)
2.3 Tube bundle
36(4)
2.4 Overall steam generator layout
40(1)
2.5 Circulation
41(5)
2.6 Other elements of the circulation system
46(3)
2.7 Feedwater inlet
49(1)
2.8 Pressure boundary design
50(3)
2.9 Conclusions
53(2)
3 Steam generator manufacturing
55(26)
J.C. Smith
3.1 Introduction, manufacturers
55(3)
3.2 Manufacturing scheduling
58(2)
3.3 Main sub-assemblies
60(8)
3.4 Major assemblies
68(5)
3.5 Final assembly and preparation for shipment
73(4)
3.6 Stress reliefs
77(1)
3.7 Inspection and testing
78(1)
3.8 Shipment
79(1)
3.9 Conclusions
80(1)
4 Thermalhydraulics, circulation, and steam-water separation in nuclear steam generators
81(26)
S. Laroche
4.1 Introduction
81(1)
4.2 Recirculating steam generators
81(20)
4.3 Once-through steam generators
101(6)
Acknowledgments
104(1)
References
104(3)
5 WWER steam generators
107(18)
L. Papp
J. Vacek
5.1 Description of WWER steam generators
107(1)
5.2 SGs degradation
107(6)
5.3 WWER SGs modifications
113(4)
5.4 Integrity of heat exchange tubes
117(8)
References
124(1)
Part Two Operation and maintenance
125(424)
6 Steam-water cycle chemistry relevant to nuclear steam generators
127(28)
A. Drexler
6.1 Introduction
127(7)
6.2 Water chemistry treatments
134(4)
6.3 Additional water chemistry measures for high SG performance
138(11)
6.4 Water chemistry monitoring and control program
149(1)
6.5 Summary
150(5)
References
151(4)
7 Corrosion problems affecting steam generator tubes in commercial water-cooled nuclear power plants
155(28)
J.A. Gorman
7.1 Introduction
155(7)
7.2 Primary side stress corrosion cracking (PWSCC)
162(3)
7.3 Denting
165(18)
References
178(5)
8 Environmental degradations in PWR steam generators
183(32)
I. de Curieres
Acronyms
183(1)
8.1 Introduction
183(1)
8.2 Primary side environmental effects
184(10)
8.3 Secondary side environmental effects
194(13)
8.4 Conclusions
207(8)
References
207(8)
9 Corrosion product transport and fouling in nuclear steam generators
215(58)
C.W. Turner
K. Khumsa-Ang
9.1 Introduction
215(1)
9.2 SG design and the effect of fouling on performance degradation
216(5)
9.3 Corrosion product transport
221(18)
9.4 Fouling of nuclear SGs---plant experience
239(11)
9.5 Fouling mechanisms---fundamental studies and modeling
250(7)
9.6 Mitigating fouling of nuclear SGs---field studies
257(5)
9.7 Summary and conclusions
262(11)
References
263(10)
10 Hideout, hideout return and crevice chemistry in nuclear steam generators
273(50)
C.W. Turner
M. Huang
A. McKay
10.1 Introduction
273(1)
10.2 Hideout and hideout return in flow-restricted regions
274(17)
10.3 Chemistry environment in flow-restricted regions
291(12)
10.4 Plant hideout return studies
303(12)
10.5 Summary and conclusions
315(8)
References
317(6)
11 Deposit accumulation in PWR steam generators
323(42)
Robert D. Varrin, Jr.
11.1 Overview
323(11)
11.2 Deposit characterization
334(10)
11.3 Deposit management
344(1)
11.4 Mechanical cleaning of PWR SGs
345(6)
11.5 Chemical cleaning of PWR SGs
351(9)
11.6 Mild cleaning of PWR SGs
360(5)
References
363(2)
12 Thermal performance degradation and heat-transfer fouling
365(40)
M. Kreider
G. White
12.1 Introduction
365(1)
12.2 Quantifying SG heat-transfer fouling
366(7)
12.3 Industry trends in SG thermal performance
373(5)
12.4 Causes of thermal performance changes
378(14)
12.5 Consequences of SG thermal performance loss
392(1)
12.6 Effects of corrosion deposit removal
393(3)
12.7 Conclusion
396(9)
References
398(7)
13 Flow-induced vibrations in nuclear steam generators
405(30)
M. Hassan
13.1 Flow characteristics
405(1)
13.2 Tube vibration characteristics
406(2)
13.3 Excitation mechanisms
408(13)
13.4 Estimation of tube bundle integrity
421(9)
13.5 Recent challenges
430(1)
13.6 Summary
431(4)
References
431(4)
14 Structural integrity assessment of nuclear steam generator
435(36)
S. Majumdar
S. Bakhtiari
Z. Zeng
C.B. Bahn
Acronyms
435(1)
Symbols
436(1)
14.1 Introduction
436(2)
14.2 Structural integrity prediction models
438(16)
14.3 Structural integrity of U-bends with flaws
454(5)
14.4 Application of equivalent rectangular crack method
459(6)
14.5 Conclusions and recommendations for future research
465(6)
Acknowledgment
467(1)
References
467(4)
15 Nuclear steam generator inspection and testing
471(24)
T. Sollier
Acronyms
471(1)
15.1 Introduction
472(1)
15.2 ISI techniques and qualification methodology
472(1)
15.3 In-service inspection
473(12)
15.4 Water tightness of the tube bundle
485(2)
15.5 Hydrostatic pressure test
487(1)
15.6 Future trends for recirculating steam generator maintenance and inspection
488(2)
15.7 Conclusion
490(5)
Acknowledgments
490(1)
References
490(5)
16 Nuclear steam generator tube inspection tools
495(16)
L. Obrutsky
16.1 Introduction
495(1)
16.2 Historical perspective
495(1)
16.3 Inspection tools
496(7)
16.4 Data analysis
503(1)
16.5 Technique qualification
504(1)
16.6 Data management
504(1)
16.7 Advanced and automatic analysis techniques
505(1)
16.8 Inspection requirements and scope
506(1)
16.9 Summary/Conclusions
507(4)
Acknowledgments
508(1)
References
508(3)
17 Nuclear steam generator fitness-for-service assessment
511(14)
L.B. Carroll
17.1 Overview
511(1)
17.2 Repair criteria for steam generator tubes
511(2)
17.3 Steam generator tube degradation assessment
513(1)
17.4 Performance criteria for steam generator tubes
514(11)
References
522(3)
18 Regulatory requirements and considerations for nuclear steam generators
525(24)
E.L. Murphy
18.1 Introduction
525(1)
18.2 Regulatory requirements and considerations for nuclear SGs in the United States
525(16)
18.3 Regulatory practices and tubing inspection requirements in Canada
541(8)
References
545(4)
Index 549
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.