Pressurized Heavy Water Reactors
Atucha II
- 1st Edition, Volume 8 - October 2, 2021
- Imprint: Elsevier
- Editor: Jovica Riznic
- Language: English
- Paperback ISBN:9 7 8 - 0 - 3 2 3 - 8 5 3 8 2 - 8
- eBook ISBN:9 7 8 - 0 - 3 2 3 - 8 5 3 8 3 - 5
Pressurized Heavy Water Reactors: Atucha-II, the eighth volume in the JSME Series on Thermal and Nuclear Power Generation, provides a comprehensive and complete review of a single… Read more
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Request a sales quotePressurized Heavy Water Reactors: Atucha-II, the eighth volume in the JSME Series on Thermal and Nuclear Power Generation, provides a comprehensive and complete review of a single type of reactor in a very accessible and practical way. The book presents a close analysis of the Atucha reactor, covering reactor physics, aging management of major components, and the role of codes in PHWR and Nuclear Regulation and Licensing. Including contemporary capabilities and challenges of nuclear technology, the book offers solutions and advice on common problems faced, guiding the reader through safe and approved processes that will help them reach suitable solutions.
Professionals involved in lifecycle assessments and researchers interested in the development and improvement of nuclear energy technologies will gain a deep understanding of PHWR nuclear reactor physics, design and licensing.
- A comprehensive reference on the latest research on Atucha Pressurized Heavy Water Reactors and their impact on sustainability goals
- Analyzes The Atucha-2 BEPU and LBLOCA
- Considers the licensing of Atucha-2, its physics and aging management of major components
Nuclear engineering and researchers focusing on PHWRs; PHWR plant designers and operators; regulators; NPP life cycle engineers; post graduate students of nuclear engineering; thermal energy engineers and researchers; national labs; government officials and agencies in power and energy policy and regulations
- Cover image
- Title page
- Table of Contents
- Copyright
- List of contributors
- About the editor
- Preface of JSME Series in Thermal and Nuclear Power Generation
- Preface to Volume 8: Pressurized Heavy Water Reactors: Atucha II
- Abbreviations and acronyms
- 1. Atucha II plant description
- Abstract
- Chapter Outline
- 1.1 Introduction
- 1.2 Plant description
- Appendix 1 Atucha II NPP technical data
- References
- 2. The best estimate plus uncertainty approach in licensing of Atucha II
- Abstract
- Chapter Outline
- 2.1 Introduction
- 2.2 Outline of Autoridad Regulatoria Nuclear licensing process
- 2.3 Outline of international practices relevant for the proposed approach
- 2.4 Proposed best estimate plus uncertainty approach for final safety analysis report accident analyses
- 2.5 Three-dimensional neutron kinetics thermal hydraulics coupled code
- 2.6 A sample case for application of the best estimate plus uncertainty approach (best estimate plus uncertainty procedure for DEGB LB-LOCA analysis)
- 2.7 Step 3—selected calculation results
- 2.8 Step 4—uncertainty analysis
- 2.9 Step 5—safety margin determination
- 2.10 Conclusions
- Acknowledgements
- Appendix 1 Survey on regulatory basis for the reactivity initiated accidents acceptance criteria
- References
- 3. Atucha II: insights from the accident analysis
- Abstract
- Chapter Outline
- 3.1 Introduction
- 3.2 The list of transients analyzed in chapter 15 of Atucha II FSAR
- 3.3 Computational tools, system configuration and selected modeling assumptions
- 3.4 System performance
- 3.5 The role of specific components, subsystems, and containment
- 3.6 Thermal-hydraulic phenomena
- 3.7 The coupled phenomena and scenarios
- 3.8 The instrumentation and control role
- 3.9 Comparison of scenarios
- 3.10 Miscellaneous insights including radiological impacts
- 3.11 Conclusion
- Acknowledgments
- Appendix A1 Additional Information About LBLOCA Analysis
- References
- Index
- Edition: 1
- Volume: 8
- Published: October 2, 2021
- Imprint: Elsevier
- No. of pages: 586
- Language: English
- Paperback ISBN: 9780323853828
- eBook ISBN: 9780323853835
JR
Jovica Riznic
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.
Affiliations and expertise
Technical Specialist, Canadian Nuclear Safety Commission (CNSC), CanadaRead Pressurized Heavy Water Reactors on ScienceDirect