Modelling of Nuclear Reactor Multi physics

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

Produk Detail:

  • Author : Christophe Demazière
  • Publisher : Academic Press
  • Pages : 368 pages
  • ISBN : 012815070X
  • Rating : 4/5 from 21 reviews
CLICK HERE TO GET THIS BOOKModelling of Nuclear Reactor Multi physics

Modelling of Nuclear Reactor Multi-physics

Modelling of Nuclear Reactor Multi-physics
  • Author : Christophe Demazière
  • Publisher : Academic Press
  • Release : 19 November 2019
GET THIS BOOKModelling of Nuclear Reactor Multi-physics

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

Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment

Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment
  • Author : Jyeshtharaj Joshi,Arun K Nayak
  • Publisher : Woodhead Publishing
  • Release : 15 June 2019
GET THIS BOOKAdvances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment

Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment presents the latest computational fluid dynamic technologies. It includes an evaluation of safety systems for reactors using CFD and their design, the modeling of Severe Accident Phenomena Using CFD, Model Development for Two-phase Flows, and Applications for Sodium and Molten Salt Reactor Designs. Editors Joshi and Nayak have an invaluable wealth of experience that enables them to comment on the development of CFD models, the technologies currently in

Fundamentals of Nuclear Reactor Physics

Fundamentals of Nuclear Reactor Physics
  • Author : Elmer E. Lewis
  • Publisher : Elsevier
  • Release : 18 January 2008
GET THIS BOOKFundamentals of Nuclear Reactor Physics

Fundamentals of Nuclear Reactor Physics offers a one-semester treatment of the essentials of how the fission nuclear reactor works, the various approaches to the design of reactors, and their safe and efficient operation . It provides a clear, general overview of atomic physics from the standpoint of reactor functionality and design, including the sequence of fission reactions and their energy release. It provides in-depth discussion of neutron reactions, including neutron kinetics and the neutron energy spectrum, as well as neutron spatial

Physics of Nuclear Reactors

Physics of Nuclear Reactors
  • Author : P. Mohanakrishnan,Om Pal Singh,K. Umasankari
  • Publisher : Academic Press
  • Release : 19 May 2021
GET THIS BOOKPhysics of Nuclear Reactors

Physics of Nuclear Reactors presents a comprehensive analysis of nuclear reactor physics. Editors P. Mohanakrishnan, Om Pal Singh, and Kannan Umasankari and a team of expert contributors combine their knowledge to guide the reader through a toolkit of methods for solving transport equations, understanding the physics of reactor design principles, and developing reactor safety strategies. The inclusion of experimental and operational reactor physics makes this a unique reference for those working and researching nuclear power and the fuel cycle in

Approach to Coupling 3-D Deterministic Neutron Transport and Full Field Computational Fluid Dynamics

Approach to Coupling 3-D Deterministic Neutron Transport and Full Field Computational Fluid Dynamics
  • Author : Matthew James Marzano
  • Publisher : Unknown Publisher
  • Release : 02 July 2022
GET THIS BOOKApproach to Coupling 3-D Deterministic Neutron Transport and Full Field Computational Fluid Dynamics

ABSTRACT: Multi-physics analyses, including coupled three-dimensional (3-D) neutron transport and full eld computational uid dynamics (CFD), represent the future in advanced modeling of reactor cores. 3-D neutron transport and full- eld CFD simulations provide highly re ned and accurate solutions based on rst principles. Such an approach incorporates the full spatial and temporal coupling of interrelated physical phenomena for more detailed reactor analysis. Ultimately, this provides an advanced analysis environment leading to improvements in the level of detail in modeling

Fundamentals of Nuclear Engineering

Fundamentals of Nuclear Engineering
  • Author : Brent J. Lewis,E. Nihan Onder,Andrew A. Prudil
  • Publisher : John Wiley & Sons
  • Release : 24 March 2017
GET THIS BOOKFundamentals of Nuclear Engineering

Fundamental of Nuclear Engineering is derived from over 25 years of teaching undergraduate and graduate courses on nuclear engineering. The material has been extensively class tested and provides the most comprehensive textbook and reference on the fundamentals of nuclear engineering. It includes a broad range of important areas in the nuclear engineering field; nuclear and atomic theory; nuclear reactor physics, design, control/dynamics, safety and thermal-hydraulics; nuclear fuel engineering; and health physics/radiation protection. It also includes the latest information that

Multi-physics Approach to the Modelling and Analysis of Molten Salt Reactors

Multi-physics Approach to the Modelling and Analysis of Molten Salt Reactors
  • Author : Lelio Luzzi,Valentino Di Marcello,Antonio Cammi
  • Publisher : Nova Novinka
  • Release : 02 July 2022
GET THIS BOOKMulti-physics Approach to the Modelling and Analysis of Molten Salt Reactors

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

OpenFOAM®

OpenFOAM®
  • Author : J. Miguel Nóbrega,Hrvoje Jasak
  • Publisher : Springer
  • Release : 24 January 2019
GET THIS BOOKOpenFOAM®

This book contains selected papers of the 11th OpenFOAM® Workshop that was held in Guimarães, Portugal, June 26 - 30, 2016. The 11th OpenFOAM® Workshop had more than 140 technical/scientific presentations and 30 courses, and was attended by circa 300 individuals, representing 180 institutions and 30 countries, from all continents. The OpenFOAM® Workshop provided a forum for researchers, industrial users, software developers, consultants and academics working with OpenFOAM® technology. The central part of the Workshop was the two-day conference, where presentations and posters on industrial applications

Molten Salt Reactors and Thorium Energy

Molten Salt Reactors and Thorium Energy
  • Author : Thomas James Dolan
  • Publisher : Woodhead Publishing
  • Release : 08 June 2017
GET THIS BOOKMolten Salt Reactors and Thorium Energy

Molten Salt Reactors is a comprehensive reference on the status of molten salt reactor (MSR) research and thorium fuel utilization. There is growing awareness that nuclear energy is needed to complement intermittent energy sources and to avoid pollution from fossil fuels. Light water reactors are complex, expensive, and vulnerable to core melt, steam explosions, and hydrogen explosions, so better technology is needed. MSRs could operate safely at nearly atmospheric pressure and high temperature, yielding efficient electrical power generation, desalination, actinide

Modeling Of Hydrogen And Hydride Formation In Zirconium Alloy Cladding Using High-fidelity Multi-physics Coupled Codes

Modeling Of Hydrogen And Hydride Formation In Zirconium Alloy Cladding Using High-fidelity Multi-physics Coupled Codes
  • Author : Michael Mankosa
  • Publisher : Unknown Publisher
  • Release : 02 July 2022
GET THIS BOOKModeling Of Hydrogen And Hydride Formation In Zirconium Alloy Cladding Using High-fidelity Multi-physics Coupled Codes

The reactor environment, in which nuclear fuel operates, requires improved multi-dimensional fuel and cladding simulation and analysis to accurately describe fuel behavior. The high-fidelity fuel performance code BISON was developed at Idaho National Laboratory (INL) to address this need. BISON is a three-dimensional finite-element based fuel performance code. In the high temperature environment of a reactor, the zirconium in the cladding undergoes waterside corrosion, releasing hydrogen in the process. Some of this hydrogen is absorbed by the cladding. Once hydrogen

Proceedings of the 12th Pacific Rim Conference on Ceramic and Glass Technology; Ceramic Transactions

Proceedings of the 12th Pacific Rim Conference on Ceramic and Glass Technology; Ceramic Transactions
  • Author : Dileep Singh,Manabu Fukushima,Young-Wook Kim,Kiyoshi Shimamura,Nobuhito Imanaka,Tatsuki Ohji,Jake Amoroso,Michael Lanagan
  • Publisher : John Wiley & Sons
  • Release : 19 April 2018
GET THIS BOOKProceedings of the 12th Pacific Rim Conference on Ceramic and Glass Technology; Ceramic Transactions

Ceramic Transactions, Volume 264, Proceedings of the 12th Pacific Rim Conference on Ceramic and Glass Technology Dileep Singh, Manabu Fukushima, Young-Wook Kim, Kiyoshi Shimamura, Nobuhito Imanaka, Tatsuki Ohji, Jake Amoroso, and Michael Lanagan; Editors This proceedings contains a collection of 32 papers presented at the 12th Pacific Rim Conference on Ceramic and Glass Technology (PacRim12), May 21-26, 2017 in Waikoloa, Hawaii. PacRim is a bi-annual conference held in collaboration with the ceramic societies of the Pacific Rim countries - The American Ceramic Society,