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El. knyga: Pressurized Heavy Water Reactors: CANDU

Volume editor (Technical Specialist, Canadian Nuclear Safety Commission (CNSC), Canada)

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Pressurized Heavy Water Reactors: CANDU, the seventh volume in the JSME Series on Thermal and Nuclear Power Generation series, provides a comprehensive and complete review of a single type of reactor in a very accessible and practical way. The book presents the full lifecycle, from design and manufacturing to operation and maintenance, also covering fitness-for-service and long-term operation. It does not relate to any specific vendor-based technology, but rather provides a broad overview of the latest technologies from a variety of active locations which will be of great value to countries invested in developing their own nuclear programs.

Including contemporary capabilities and challenges of nuclear technology, the book offers practical solutions to common problems faced, along with the safe and approved processes to reach suitable solutions. Professionals involved in nuclear power plant lifecycle assessment and researchers interested in the development and improvement of nuclear energy technologies will gain a deep understanding of PHWR nuclear reactor physics, chemistry and thermal-hydraulic properties.

  • Provides a complete reference dedicated to the latest research on Pressurized Heavy Water Reactors and their economic and environmental benefits
  • Goes beyond CANDU reactors to analyze the popular German and Indian designs, as well as plant design in Korea, Romania, China and Argentina
  • Spans all phases of the nuclear power plant lifecycle, from design, manufacturing, operation, maintenance and long-term operation
List of contributors
xi
About the editor xiii
Preface of JSME Series in Thermal and Nuclear Power Generation xv
Preface to Volume 7: Pressurized Heavy Water Reactors: CANDU xvii
1 Introduction. World energy production and the contribution of PHWRs
1(44)
R.B. Duffey
I.L. Pioro
R. Pioro
1.1 Status of electricity generation in the world and selected countries
1(8)
1.2 Pressurized heavy water reactors: typical performance in Canada
9(2)
1.3 Current status, advantages, and challenges of nuclear-powered reactors
11(2)
1.4 Global operating reactor data
13(4)
1.5 The history and global context of pressurized heavy water reactors
17(4)
1.6 Pressurized heavy water reactors in operation
21(1)
1.7 Current activities in PHWRs, and modem nuclear power reactors and plants, including PWRs, BWRs, AGRs, LGRs, and SFRs
21(1)
1.8 Details on present and proposed pressurized heavy water reactors
21(9)
1.9 Summary of the pressurized heavy water reactor status and issues going forward
30(1)
1.10 Pressurized heavy water reactors immediate and future path
31(5)
1.11 Conclusion
36(1)
1.12 Nomenclature
37(8)
Appendix: Additional pressurized heavy water reactor information sources
39(1)
References
40(5)
2 Nuclear fuel
45(24)
E. Nihan Onder
2.1 Nuclear power reactors and their fuels
46(2)
2.2 Nuclear fuel materials
48(1)
2.3 Fuel-cladding material
49(1)
2.4 Fuel pellet, element, and assembly/bundle
50(3)
2.5 Fuel performance
53(7)
2.6 Fuel failure mechanisms and fuel failures
60(1)
2.7 Fuel safety and acceptance criteria
61(2)
2.8 Advanced fuel concept
63(6)
Acknowledgments
67(1)
References
67(2)
3 Zr-2.5Nb pressure tubes in CANDU* reactors
69(66)
Nicolas Christodoulou
3.1 Introduction
70(1)
3.2 Manufacturing background--resulting microstructural features-- microchemistry
71(6)
3.3 CANDU fuel channel design
77(3)
3.4 In-reactor deformation of pressure tubes
80(7)
3.5 Variability of pressure tubes
87(2)
3.6 Parameters affecting in-reactor deformation
89(15)
3.7 Mechanisms of irradiation-induced deformation
104(2)
3.8 Modeling pressure tube deformation
106(11)
3.9 Finite element methods
117(7)
3.10 Concluding remarks
124(11)
Acknowledgments
126(1)
References
126(9)
4 Computational modeling of in-reactor deformation in CANDU* fuel channels
135(36)
S.R. Prabhu
M.D. Pandey
Nicolas Christodoulou
4.1 Introduction
136(2)
4.2 Pressure tube deformation
138(3)
4.3 3D finite element analysis of in-reactor fuel channel deformation
141(10)
4.4 Finite element analysis output
151(7)
4.5 Comparison between 3D versus ID finite element analysis results
158(2)
4.6 3D finite element analysis results based on different fuel channel configurations
160(2)
4.7 Calibration of finite element model
162(3)
4.8 Conclusion
165(6)
Acknowledgments
167(1)
References
168(3)
5 Design and aging management for feeder pipe and feeder supports
171(58)
Seyun Eom
Jovica Riznic
Thambiayah Nitheanandan
Doo-Ho Cho
Heather Taylor
Ming Li
5.1 Introduction
172(1)
5.2 Feeder design and bend manufacturing
173(16)
5.3 Operating experience of feeders
189(4)
5.4 Aging management
193(29)
5.5 Practices for new feeders for refurbishment
222(7)
References
225(4)
6 Steam generators
229(46)
James Charles Smith
6.1 Introduction
229(1)
6.2 General description of pressurized heavy water reactor steam generators
230(1)
6.3 Sizes of pressurized heavy water reactor steam generators, including comparison to pressurized water reactor steam generators
231(1)
6.4 History and evolution of pressurized heavy water reactor steam generators
232(2)
6.5 Design requirements and philosophy, high circulation ratio, conservative design limits
234(4)
6.6 Tube bundle sizing and configuration, including integral preheater designs
238(4)
6.7 Tube materials used in pressurized heavy water reactor steam generators
242(4)
6.8 Tube supports in pressurized heavy water reactor steam generators
246(2)
6.9 SteanjAvater separators
248(3)
6.10 Circulation, transient behavior, stability, and tube vibration
251(4)
6.11 Water chemistry and corrosion
255(3)
6.12 Performance, maintenance, and reliability
258(3)
6.13 Pressure boundary and manufacturing processes
261(7)
6.14 Replacement of pressurized heavy water reactor steam generators
268(3)
6.15 Application of pressurized heavy water reactor steam generator technology to pressurized water reactors
271(2)
6.16 Summary
273(2)
7 Electrical power systems
275(12)
Nadine El Dabaghi
Jasmina Vucetic
7.1 General
276(1)
7.2 Design principles of a CANDU electrical power systems
276(1)
7.3 Plant electrical power systems overview
276(1)
7.4 CANDU philosophy
277(1)
7.5 Classes of power
278(1)
7.6 Standby generators
279(1)
7.7 The emergency power supply system
279(2)
7.8 Alternate alternating current power supply in response to the Fukushima events
281(1)
7.9 Common and unit concepts in a multiunit station
282(1)
7.10 Main power output
283(1)
7.11 Automatic transfer system
284(1)
7.12 Switchyard and synchronizing to the grid
285(1)
7.13 Highlights of this chapter
285(2)
Acknowledgments
286(1)
8 Radiation protection
287(28)
Edward Waller
8.1 Introduction
287(2)
8.2 Core concepts for radiation protection
289(17)
8.3 Considerations for pressurized heavy water reactor radiation protection
306(6)
8.4 Summary
312(3)
References
312(1)
Further reading
313(2)
9 Fitness for service and related concepts
315(14)
John P.S. Froats
Paul Spekkens
9.1 Introduction
315(1)
9.2 Roots in Canadian standards and regulatory documents
316(1)
9.3 Definitions of key terms
317(2)
9.4 The continuum from design to decommissioning
319(1)
9.5 Steps in conducting a fitness for service assessment
320(1)
9.6 The perils of projections
321(3)
9.7 Code effective dates
324(1)
9.8 How critical is configuration management?
325(1)
9.9 Limitations and traps in fitness for service declarations
326(3)
10 Fitness-for-service guidelines
329(58)
Michael J. Kozluk
10.1 Introduction
329(14)
10.2 Pressure tubes
343(7)
10.3 Steam generator tubes
350(17)
10.4 Feeder pipes
367(20)
Glossary
382(1)
Symbols
383(1)
References
383(4)
11 Overview of the Canadian Nuclear Safety Commission--Canada's nuclear regulator
387(12)
Kevin Lee
Douglass Miller
11.1 Canadian Nuclear Safety Commission's mandate and role
387(1)
11.2 Organizational structure
388(2)
11.3 Nuclear power plants
390(6)
11.4 Application of the regulatory framework
396(3)
References
398(1)
12 The extended operation and life extension project of Embalse Nuclear Power Plant--an account from a regulator's perspective
399(30)
Geronimo Poletto
Reinaldo Valle Cepero
12.1 First operating cycle
401(1)
12.2 Life extension decision
401(1)
12.3 Extended operation
402(1)
12.4 Regulatory actions
403(9)
12.5 Embalse's life extension
412(1)
12.6 General strategy for licensing
413(1)
12.7 Description of the life extension project
413(1)
12.8 Main refurbishment activities--licensing agreements and regulatory oversight
414(2)
12.9 Evolution of activities for the agreed licensing
416(1)
12.10 Planning and scheduling
416(1)
12.11 Organizational structure of the utility for refurbishment
416(1)
12.12 Condition assessments of the unit
417(1)
12.13 Environmental radiological impact assessment
417(1)
12.14 Environmental qualification program
418(1)
12.15 Agingmanagement program
418(1)
12.16 Management of design changes and improvements related to safety
418(2)
12.17 Uni repowering
420(1)
12.18 Moderator heat exchangers replacement
420(1)
12.19 Severe accident management program
420(1)
12.20 Seismic reassessment
421(1)
12.21 Reactor retubing
421(1)
12.22 Steam generators replacement
422(2)
12.23 Training and certification of personnel
424(1)
12.24 Retum-to-service program
425(4)
13 Cernavoda--CANDU nuclear power plants in Romania
429(14)
Madalina Cristiana Coca
13.1 Historical perspective
429(1)
13.2 Legislative and regulatory framework for nuclear safety in Romania
430(2)
13.3 Safety philosophy and defense-in-depth of the CANDU nuclear power plants
432(8)
13.4 Safety upgrades post-Fukushima
440(3)
Bibliography
441(2)
14 Pressurized heavy water reactors probabilistic safety assessment
443(34)
Alexander Trifanov
14.1 Introduction
443(3)
14.2 Level 1 probabilistic safety assessment for internal events at full power
446(15)
14.3 Level 2 probabilistic safety assessment for internal events at full power
461(6)
14.4 Outage probabilistic safety assessment
467(3)
14.5 Internal fire probabilistic safety assessment
470(2)
14.6 Internal flood probabilistic safety assessment
472(1)
14.7 Seismic probabilistic safety assessment
473(1)
14.8 High Wind probabilistic safety assessment
474(3)
References
475(2)
15 Severe accident prevention and mitigation in pressurized heavy water reactors
477(32)
Samuel Hilton Gyepi-Garbrah
Thambiayah Nitheanandan
15.1 Introduction
478(3)
15.2 Basic phenomena and behavior involving severe accident in pressurized heavy water reactors
481(4)
15.3 Pressurized heavy water reactors and accident progression core damage states
485(5)
15.4 Behavior and phenomena common and different from light water reactors and pressurized heavy water reactors
490(4)
15.5 Accident prevention in pressurized heavy water reactors
494(2)
15.6 Accident mitigation in pressurized heavy water reactors
496(4)
15.7 Severe accident management program in pressurized heavy water reactors
500(2)
15.8 Research, development, and challenges for the future of pressurized heavy water reactors
502(1)
15.9 Conclusion
502(7)
Acronyms
502(1)
References
503(6)
Index 509
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.