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Modelling of Nuclear Reactor Multi physics

Modelling of Nuclear Reactor Multi physics
  • Author : Christophe Demazière
  • Publsiher : Academic Press
  • Release : 19 November 2019
  • ISBN : 012815070X
  • Pages : 368 pages
  • Rating : 4/5 from 21 ratings
GET THIS BOOKModelling of Nuclear Reactor Multi physics

Summary:
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


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

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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 : 24 October 2021
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

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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 : Antonio Cammi,Lelio Luzzi,Valentino Di Marcello
  • Publisher : Nova Science Publishers
  • Release : 01 February 2012
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

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Nuclear Reactor Multi-physics Simulations with Coupled MCNP5 and STAR-CCM+

Nuclear Reactor Multi-physics Simulations with Coupled MCNP5 and STAR-CCM+
  • Author : Jeffrey N. Cardoni
  • Publisher : Anonim
  • Release : 24 October 2021
GET THIS BOOKNuclear Reactor Multi-physics Simulations with Coupled MCNP5 and STAR-CCM+

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

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Verification, Validation and Uncertainty Quantification of Multi-Physics Modeling of Nuclear Reactors

Verification, Validation and Uncertainty Quantification of Multi-Physics Modeling of Nuclear Reactors
  • Author : Maria Avramova,Kostadin Ivanov
  • Publisher : Woodhead Publishing Series in
  • Release : 15 September 2018
GET THIS BOOKVerification, Validation and Uncertainty Quantification of Multi-Physics Modeling of Nuclear Reactors

Verification, Validation and Uncertainty Quantification in Multi-Physics Modeling of Nuclear Reactors is a key reference for those tasked with ensuring the credibility and reliability of engineering models and simulations for the nuclear industry and nuclear energy research. Sections discuss simulation challenges and revise key definitions, concepts and terminology. Chapters cover solution verification, the frontier discipline of multi-physics coupling verification, model validation and its applications to single and multi-scale models, and uncertainty quantification. This essential guide will greatly assist engineers, scientists,

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Thermal-Hydraulics of Water Cooled Nuclear Reactors

Thermal-Hydraulics of Water Cooled Nuclear Reactors
  • Author : Francesco D'Auria
  • Publisher : Woodhead Publishing
  • Release : 18 May 2017
GET THIS BOOKThermal-Hydraulics of Water Cooled Nuclear Reactors

Thermal Hydraulics of Water-Cooled Nuclear Reactors reviews flow and heat transfer phenomena in nuclear systems and examines the critical contribution of this analysis to nuclear technology development. With a strong focus on system thermal hydraulics (SYS TH), the book provides a detailed, yet approachable, presentation of current approaches to reactor thermal hydraulic analysis, also considering the importance of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors. Part One presents the background to nuclear

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The Development of a Thermal Hydraulic Feedback Mechanism with a Quasi-fixed Point Iteration Scheme for Control Rod Position Modeling for the TRIGSIMS-TH Application

Nuclear reactor design incorporates the study and application of nuclear physics, nuclear thermal hydraulic and nuclear safety. Theoretical models and numerical methods implemented in computer programs are utilized to analyze and design nuclear reactors. The focus of this PhD study's is the development of an advanced high-fidelity multi-physics code system to perform reactor core analysis for design and safety evaluations of research TRIGA-type reactors. The fuel management and design code system TRIGSIMS was further developed to fulfill the function of

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Computational Fluid Dynamics

Computational Fluid Dynamics
  • Author : Adela Ionescu
  • Publisher : BoD – Books on Demand
  • Release : 14 February 2018
GET THIS BOOKComputational Fluid Dynamics

This book is the result of a careful selection of contributors in the field of CFD. It is divided into three sections according to the purpose and approaches used in the development of the contributions. The first section describes the "high-performance computing" (HPC) tools and their impact on CFD modeling. The second section is dedicated to "CFD models for local and large-scale industrial phenomena." Two types of approaches are basically contained here: one concerns the adaptation from global to local

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Validation and Calibration of Nuclear Thermal Hydraulics Multiscale Multiphysics Models - Subcooled Flow Boiling Study

In addition to validation data plan, development of advanced techniques for calibration and validation of complex multiscale, multiphysics nuclear reactor simulation codes are a main objective of the CASL VUQ plan. Advanced modeling of LWR systems normally involves a range of physico-chemical models describing multiple interacting phenomena, such as thermal hydraulics, reactor physics, coolant chemistry, etc., which occur over a wide range of spatial and temporal scales. To a large extent, the accuracy of (and uncertainty in) overall model predictions

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Investigation of Bond Graphs for Nuclear Reactor Simulations

Investigation of Bond Graphs for Nuclear Reactor Simulations
  • Author : Eugeny Sosnovsky
  • Publisher : Anonim
  • Release : 24 October 2021
GET THIS BOOKInvestigation of Bond Graphs for Nuclear Reactor Simulations

This work proposes a simple and effective approach to modeling multiphysics nuclear reactor problems using bond graphs. The conventional method of modeling the coupled multiphysics transients in nuclear reactors is operator splitting, which treats the single physics individually and exchanges the information at every time step. This approach has limited accuracy, and so there is interest in the development of methods for fully coupled physics simulation. The bond graph formalism was first introduced to solve the multiphysics problem in electromechanical

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Nuclear Systems

Nuclear Systems
  • Author : Neil E. Todreas,Mujid S Kazimi
  • Publisher : CRC Press
  • Release : 24 October 2021
GET THIS BOOKNuclear Systems

Nuclear power is in the midst of a generational change—with new reactor designs, plant subsystems, fuel concepts, and other information that must be explained and explored—and after the 2011 Japan disaster, nuclear reactor technologies are, of course, front and center in the public eye. Written by leading experts from MIT, Nuclear Systems Volume I: Thermal Hydraulic Fundamentals, Second Edition provides an in-depth introduction to nuclear power, with a focus on thermal hydraulic design and analysis of the nuclear core.

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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 : Anonim
  • Release : 24 October 2021
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

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Thermal Hydraulic Characteristics of Fuel Defects in Plate Type Nuclear Research Reactors

Turbulent flow coupled with heat transfer is investigated for a High Flux Isotope Reactor (HFIR) fuel plate. The Reynolds Averaged Navier-Stokes Models are used for fluid dynamics and the transfer of heat from a thermal nuclear fuel plate using the Multi-physics code COMSOL. Simulation outcomes are compared with experimental data from the Advanced Neutron Source Reactor Thermal Hydraulic Test Loop. The computational results for the High Flux Isotope Reactor core system provide a more physically accurate simulation of this system

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Multi-Physics Demonstration Problem with the SHARP Reactor Simulation Toolkit

Multi-Physics Demonstration Problem with the SHARP Reactor Simulation Toolkit
  • Author : Anonim
  • Publisher : Anonim
  • Release : 24 October 2021
GET THIS BOOKMulti-Physics Demonstration Problem with the SHARP Reactor Simulation Toolkit

This report describes to employ SHARP to perform a first-of-a-kind analysis of the core radial expansion phenomenon in an SFR. This effort required significant advances in the framework Multi-Physics Demonstration Problem with the SHARP Reactor Simulation Toolkit used to drive the coupled simulations, manipulate the mesh in response to the deformation of the geometry, and generate the necessary modified mesh files. Furthermore, the model geometry is fairly complex, and consistent mesh generation for the three physics modules required significant effort.

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