Modelling of Nuclear Reactor Multiphysics: From Local Balance Equations to Macroscopic Models in Neutronics and Thermal-Hydraulics is an accessible guide to the advanced methods used to model nuclear reactor systems. The book addresses the frontier discipline of neutronic/thermal-hydraulic modelling of nuclear reactor cores, presenting the main techniques in a generic manner and for practical reactor calculations.
The modelling of nuclear reactor systems is one of the most challenging tasks in complex system modelling, due to the many different scales and intertwined physical phenomena involved. The nuclear industry as well as the research institutes and universities heavily rely on the use of complex numerical codes. All the commercial codes are based on using different numerical tools for resolving the various physical fields, and to some extent the different scales, whereas the latest research platforms attempt to adopt a more integrated approach in resolving multiple scales and fields of physics. The book presents the main algorithms used in such codes for neutronic and thermal-hydraulic modelling, providing the details of the underlying methods, together with their assumptions and limitations. Because of the rapidly expanding use of coupled calculations for performing safety analyses, the analysists should be equally knowledgeable in all fields (i.e. neutron transport, fluid dynamics, heat transfer).
The first chapter introduces the book's subject matter and explains how to use its digital resources and interactive features. The following chapter derives the governing equations for neutron transport, fluid transport, and heat transfer, so that readers not familiar with any of these fields can comprehend the book without difficulty. The book thereafter examines the peculiarities of nuclear reactor systems and provides an overview of the relevant modelling strategies. Computational methods for neutron transport, first at the cell and assembly levels, then at the core level, and for one-/two-phase flow transport and heat transfer are treated in depth in respective chapters. The coupling between neutron transport solvers and thermal-hydraulic solvers for coarse mesh macroscopic models is given particular attention in a dedicated chapter. The final chapter summarizes the main techniques presented in the book and their interrelation, then explores beyond state-of-the-art modelling techniques relying on more integrated approaches.
- Covers neutron transport, fluid dynamics, and heat transfer, and their interdependence, in one reference
- Analyses the emerging area of multi-physics and multi-scale reactor modelling
- Contains 71 short videos explaining the key concepts and 77 interactive quizzes allowing the readers to test their understanding
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1. Introduction 2. Transport phenomena in nuclear reactors 3. Neutron transport: cell and assembly calculations 4. Neutron transport: core calculations 5. One-/two-phase flow transport and heat transfer 6. Neutronic/thermal-hydraulic coupling 7. Conclusion
Christophe Demazière is a Full Professor at Chalmers University of Technology, Sweden, where he leads the DREAM (Deterministic REActor Modelling ) task force at the Department of Physics. DREAM is a multidisciplinary group with expertise in neutron transport, fluid dynamics, heat transfer, and numerical methods. The group tackles the modelling of nuclear reactors from an integrated viewpoint (taking the multi-physics and multi-scale aspects into account). He has more than 20 years of experience in nuclear reactor modelling, covering reactor statics, reactor dynamics, and neutron noise. He has been educating MSc students, PhD students and nuclear engineers in nuclear reactor modelling. He is a referee for various journals including Nuclear Science and Engineering, Nuclear Technology, Annals of Nuclear Energy, Progress in Nuclear Energy and Nuclear Engineering and Design. He is a member of the American Nuclear Society (ANS).