Modelling of Nuclear Reactor Multiphysics: From Local Balance Equations to Macroscopic Models in Neutronics and Thermal-Hydraulics

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 based on their multiphysics and multi-scale nature. The book addresses the frontier discipline of neutronic/thermal-hydraulic coupling for nuclear reactor core analysis, presenting the main modelling techniques in a generic manner (i.e. not specific to any code system) and for practical reactor calculations (e.g. those performed utility companies for core-following and safety assessment). 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, examines the peculiarities of nuclear reactor systems and provides an overview of the relevant modelling strategies. Computational methods for neutron transport, core calculations and one-/two-phase flow transport and heat transfer are then treated in depth, as well as the coupling between neutron transport solvers and thermal-hydraulic solvers for coarse mesh macroscopic models. 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 multiphysics and multi-scale approaches. This essential and authoritative interactive text will be enable engineers, analysts and students engaging in the complex task of nuclear reactor systems' modelling to access the codes used in the nuclear industry and academia with confidence. uniquely and crucially for nuclear researchers and students, three key areas - neutron transport, fluid dynamics, and heat transfer - and their interdependence are presented within the same bookcovers the emerging area of multiphysics reactor modelling, from the viewpoint of reactor analysts' information needscontains seventy short videos explaining key concepts and sixty interactive quizzes, allowing readers to quickly access and revise the concepts presented in the book and test their understanding INDICE: 1. Introduction2. Transport phenomena in nuclear reactors3. Neutron transport: cell and assembly calculations4. Neutron transport: core calculations5. One-/two-phase flow transport and heat transfer6. Neutronic/thermal-hydraulic coupling7. Conclusion

• ISBN: 978-0-12-815069-6
• Editorial: Academic Press
• Encuadernacion: Rústica
• Páginas: 300
• Fecha Publicación: 01/11/2019
• Nº Volúmenes: 1
• Idioma: Inglés