Modelling of Nuclear Reactor Multi-physics - read free eBook in online reader or directly download on the web page. Select files or add your book in reader. Download and read online ebook Modelling of Nuclear Reactor Multi-physics write by Christophe Demazière. This book was released on 2019-11-19. Modelling of Nuclear Reactor Multi-physics available in PDF, EPUB and Kindle. 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
Multi-Physics and Multi-Scale Modeling and Simulation Methods for Nuclear Reactor Application
Multi-Physics and Multi-Scale Modeling and Simulation Methods for Nuclear Reactor Application - read free eBook in online reader or directly download on the web page. Select files or add your book in reader. Download and read online ebook Multi-Physics and Multi-Scale Modeling and Simulation Methods for Nuclear Reactor Application write by Xingjie Peng. This book was released on 2024-02-28. Multi-Physics and Multi-Scale Modeling and Simulation Methods for Nuclear Reactor Application available in PDF, EPUB and Kindle. A nuclear reactor operates in an environment where complex multi-physics and multi-scale phenomena exist, and it requires consideration of coupling among neutronics, thermal hydraulics, fuel performance, chemical dynamics, and coupling between the reactor core and first circuit. Safe, reliable, and economical operation can be achieved by leveraging high-fidelity numerical simulation, and proper considerations for coupling among different physics and required to provide powerful numerical simulation tools. In the past simplistic models for some of the physics phenomena are used, with the recent development of advanced numerical methods, software design, and high-performance computing power, the appeal of multi-physics and multi-scale modeling and simulation has been broadened.
Multi-Physics Approach to the Modelling and Analysis of Molten Salt Reactors
Multi-Physics Approach to the Modelling and Analysis of Molten Salt Reactors - read free eBook in online reader or directly download on the web page. Select files or add your book in reader. Download and read online ebook Multi-Physics Approach to the Modelling and Analysis of Molten Salt Reactors write by Antonio Cammi. This book was released on 2012-02-01. Multi-Physics Approach to the Modelling and Analysis of Molten Salt Reactors available in PDF, EPUB and Kindle. Multi-Physics Modelling (MPM) is an innovative simulation technique that looks very promising for the employment in the field of nuclear engineering as an integrative analysis support in the design development of current and innovative nuclear reactors. This book presents a Multi-Physics Modelling (MPM) approach to the analysis of nuclear reactor core behaviour, developed to study the coupling between neutronics and thermo-hydrodynamics. Reference is made to the Molten Salt Reactor, one of the innovative nuclear systems under development in the framework of the Generation IV International Forum, but the same methodology can be applied to other reactor systems.
Nuclear Reactor Multi-physics Simulations with Coupled MCNP5 and STAR-CCM+
Nuclear Reactor Multi-physics Simulations with Coupled MCNP5 and STAR-CCM+ - read free eBook in online reader or directly download on the web page. Select files or add your book in reader. Download and read online ebook Nuclear Reactor Multi-physics Simulations with Coupled MCNP5 and STAR-CCM+ write by Jeffrey N. Cardoni. This book was released on 2011. Nuclear Reactor Multi-physics Simulations with Coupled MCNP5 and STAR-CCM+ available in PDF, EPUB and Kindle. The MCNP5 Monte Carlo particle transport code has been coupled to the computational fluid dynamics code, STAR-CCM+, to provide a high fidelity multi-physics simulation tool for analyzing the steady state properties of a PWR core. The codes are executed separately and coupled externally through a Perl script. The Perl script automates the exchange of temperature, density, and volumetric heating information between the codes using ASCII text data files. Fortran90 and Java utility programs the assist job automation with data post-processing and file management. The MCNP5 utility code, MAKXSF, pre-generates temperature dependent cross section libraries for the thermal feedback calculations. The MCNP50́3STAR-CCM+ coupled simulation tool, dubbed MULTINUKE, is applied to two steady state, PWR models to demonstrate its usage and capabilities. The first demonstration model, a single fuel element surrounded by water, consists of 9,984 CFD cells and 7,489 neutronic cells. The second model is a 3 x 3 PWR lattice model, consisting of 89,856 CFD cells and 67,401 neutronic cells. Fission energy deposition (fission and prompt gamma heating) is tallied over all UO2 cells in the models using the F7:N tally in MCNP5. The demonstration calculations show reasonable results that agree with PWR values typically reported in literature. Temperature and fission reaction rate distributions are realistic and intuitive. Reactivity coefficients are also deemed reasonable in comparison to historically reported data. Mesh count is held to a minimum in both models to expedite computation time on a 2.8 GHz quad core machine with 1 GB RAM. The simulations on a quad core machine indicate that a massively parallelized implementation of MULTINUKE could be used to assess larger multi-million cell models with more complicated, time-dependent neutronic and thermal-hydraulic feedback effects.
Science Based Integrated Approach to Advanced Nuclear Fuel Development - Integrated Multi-scale Multi-physics Hierarchical Modeling and Simulation Framework Part III
Science Based Integrated Approach to Advanced Nuclear Fuel Development - Integrated Multi-scale Multi-physics Hierarchical Modeling and Simulation Framework Part III - read free eBook in online reader or directly download on the web page. Select files or add your book in reader. Download and read online ebook Science Based Integrated Approach to Advanced Nuclear Fuel Development - Integrated Multi-scale Multi-physics Hierarchical Modeling and Simulation Framework Part III write by . This book was released on 2010. Science Based Integrated Approach to Advanced Nuclear Fuel Development - Integrated Multi-scale Multi-physics Hierarchical Modeling and Simulation Framework Part III available in PDF, EPUB and Kindle. Advancing the performance of Light Water Reactors, Advanced Nuclear Fuel Cycles, and Advanced Reactors, such as the Next Generation Nuclear Power Plants, requires enhancing our fundamental understanding of fuel and materials behavior under irradiation. The capability to accurately model the nuclear fuel systems to develop predictive tools is critical. Not only are fabrication and performance models needed to understand specific aspects of the nuclear fuel, fully coupled fuel simulation codes are required to achieve licensing of specific nuclear fuel designs for operation. The backbone of these codes, models, and simulations is a fundamental understanding and predictive capability for simulating the phase and microstructural behavior of the nuclear fuel system materials and matrices. In this paper we review the current status of the advanced modeling and simulation of nuclear reactor cladding, with emphasis on what is available and what is to be developed in each scale of the project, how we propose to pass information from one scale to the next, and what experimental information is required for benchmarking and advancing the modeling at each scale level.
