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Multiphysics In Nuclear Science And Engineering

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Modelling of Nuclear Reactor Multi physics

Modelling of Nuclear Reactor Multi physics Book
Author : Christophe Demazière
Publisher : Academic Press
Release : 2019-11-19
ISBN : 012815070X
Language : En, Es, Fr & De

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Book Description :

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

Particle Methods for Multi Scale and Multi Physics

Particle Methods for Multi Scale and Multi Physics Book
Author : M B Liu,G R Liu
Publisher : World Scientific
Release : 2015-12-28
ISBN : 9814571717
Language : En, Es, Fr & De

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Book Description :

Multi-scale and multi-physics modeling is useful and important for all areas in engineering and sciences. Particle Methods for Multi-Scale and Multi-Physics systematically addresses some major particle methods for modeling multi-scale and multi-physical problems in engineering and sciences. It contains different particle methods from atomistic scales to continuum scales, with emphasis on molecular dynamics (MD), dissipative particle dynamics (DPD) and smoothed particle hydrodynamics (SPH). This book covers the theoretical background, numerical techniques and many interesting applications of the particle methods discussed in this text, especially in: micro-fluidics and bio-fluidics (e.g., micro drop dynamics, movement and suspension of macro-molecules, cell deformation and migration); environmental and geophysical flows (e.g., saturated and unsaturated flows in porous media and fractures); and free surface flows with possible interacting solid objects (e.g., wave impact, liquid sloshing, water entry and exit, oil spill and boom movement). The presented methodologies, techniques and example applications will benefit students, researchers and professionals in computational engineering and sciences. Contents:IntroductionMolecular DynamicsDissipative Particle Dynamics — MethodologyDissipative Particle Dynamics — ApplicationsSmoothed Particle Hydrodynamics — MethodologySmoothed Particle Hydrodynamics — ApplicationsThree Typical Particle Methods Readership: Undergraduates, graduates, researchers, and professionals studying/dealing with fluid mechanics, numerical analysis and computational mathematics, engineering mechanics, ocean engineering, mechanical engineering. Key Features:The authors have many years of experience in meshfree and particle methods, and are renowned scientists in related areas, with highly cited publications. This can greatly attracts fellow researchers from all around the world to probe the latest development on current major particle methodsThe authors have authored numerous technical publications, and many popular books. They truly understand what the fellow researchers think and wantThe authors have extensive network in academics and research. It is comparatively easy to introduce the book to professional organizations, international conferences, and different academic bodies such as universities and research institutesKeywords:Computer Modeling;Numerical Methods;Meshfree Particle Methods;Smoothed Particle Hydrodynamics;Dissipative Particle Dynamics;Molecular Dynamics

Issues in Water and Power Engineering 2013 Edition

Issues in Water and Power Engineering  2013 Edition Book
Author : Anonim
Publisher : ScholarlyEditions
Release : 2013-05-01
ISBN : 1490108327
Language : En, Es, Fr & De

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Book Description :

Issues in Water and Power Engineering / 2013 Edition is a ScholarlyEditions™ book that delivers timely, authoritative, and comprehensive information about Fusion Engineering. The editors have built Issues in Water and Power Engineering: 2013 Edition on the vast information databases of ScholarlyNews.™ You can expect the information about Fusion Engineering in this book to be deeper than what you can access anywhere else, as well as consistently reliable, authoritative, informed, and relevant. The content of Issues in Water and Power Engineering: 2013 Edition has been produced by the world’s leading scientists, engineers, analysts, research institutions, and companies. All of the content is from peer-reviewed sources, and all of it is written, assembled, and edited by the editors at ScholarlyEditions™ and available exclusively from us. You now have a source you can cite with authority, confidence, and credibility. More information is available at http://www.ScholarlyEditions.com/.

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

Multi physics Approach to the Modelling and Analysis of Molten Salt Reactors Book
Author : Lelio Luzzi,Valentino Di Marcello,Antonio Cammi
Publisher : Nova Novinka
Release : 2012
ISBN : 9781614700005
Language : En, Es, Fr & De

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Book Description :

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 Multiphysics Via Bond Graph Formalism

Nuclear Reactor Multiphysics Via Bond Graph Formalism Book
Author : Eugeny Sosnovsky,Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Publisher : Unknown
Release : 2014
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Book Description :

This work proposes a simple and effective approach to modeling nuclear reactor multiphysics problems using bond graphs. Conventional multiphysics simulation paradigms normally use operator splitting, which treats the individual physics separately and exchanges the information at every time step. This approach has limited accuracy, and so recently, there has been an increased interest in fully coupled physics simulation. The bond graph formalism has recently been suggested as a potential paradigm for reactor multiphysics simulation; this work develops the tools necessary to utilize bond graphs for practical transient reactor analysis. The bond graph formalism was first introduced to solve the multiphysics problem in electromechanical systems. Over the years, it has been used in many fields including nuclear engineering, but with limited scope due to its perceived impracticality in large systems. Bond graph formalism works by first representing a discretized multiphysics system using a group of graph elements, connected with bonds; the bonds transport conserved quantities, and the elements impose the relations between them. The representation can be automatically converted into a state derivative vector, which can be integrated in time. In an earlier work, the bond graph formalism was first applied to neutron diffusion, and coupled to diffusive heat transfer in a 1D slab reactor. In this work, methods are developed to represent, using bond graphs, 2D and 3D multigroup neutron diffusion with precursors, nonlinear point kinetics, and basic nearly-incompressible 1D flow for fully coupled reactor simulation. High-performance, matrix-based bond graph processing methods were developed to support the simulation of medium- and large-scale problems. A pressurized water reactor point kinetics, single-channel rod ejection benchmark problem was used to verify the nonlinear point kinetics representation. 2D and 3D boiling water reactor control blade drop problems were also successfully simulated with the matrix-based bond graph processing code. The code demonstrated 3rd-order convergence in time, a very desirable property of fully coupled time integrators.

Computational Techniques for Multiphase Flows

Computational Techniques for Multiphase Flows Book
Author : Guan Heng Yeoh,Jiyuan Tu
Publisher : Butterworth-Heinemann
Release : 2019-02-27
ISBN : 0081024541
Language : En, Es, Fr & De

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Book Description :

Computational Techniques for Multiphase Flows, Second Edition, provides the latest research and theories covering the most popular multiphase flows The book begins with an overview of the state-of-the-art techniques for multiple numerical methods in handling multiphase flow, compares them, and finally highlights their strengths and weaknesses. In addition, it covers more straightforward, conventional theories and governing equations in early chapters, moving on to the more modern and complex computational models and tools later in the book. It is therefore accessible to those who may be new to the subject while also featuring topics of interest to the more experienced researcher. Mixed or multiphase flows of solid/liquid or solid/gas are commonly found in many industrial fields, and their behavior is complex and difficult to predict in many cases. The use of computational fluid dynamics (CFD) has emerged as a powerful tool for understanding fluid mechanics in multiphase reactors, which are widely used in the chemical, petroleum, mining, food, automotive, energy, aerospace and pharmaceutical industries. This revised edition is an ideal reference for scientists, MSc students and chemical and mechanical engineers in these areas. Includes updated chapters in addition to a brand-new section on granular flows. Features novel solution methods for multiphase flow, along with recent case studies. Explains how and when to use the featured technique and how to interpret the results and apply them to improving applications.

Investigation of Bond Graphs for Nuclear Reactor Simulations

Investigation of Bond Graphs for Nuclear Reactor Simulations Book
Author : Eugeny Sosnovsky
Publisher : Unknown
Release : 2010
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Book Description :

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 systems. Over the years, it has been used in many fields including nuclear engineering, but with limited scope due to its perceived impracticality in large systems. In this work, the bond graph formalism is for the first time applied to neutron transport, and coupled to heat transfer in a nuclear reactor. Fully coupled 1D diffusion reaction model is derived using bond graphs, and the transient solution obtained using a proof-of-concept bond graph processing code. The bond graph-based approach to coupled nuclear reactor simulation was shown to be accurate and stable. Suggestions are made for the expansion of the approach to larger problems and higher fidelity simulations.

BERRU Predictive Modeling

BERRU Predictive Modeling Book
Author : Dan Gabriel Cacuci
Publisher : Springer
Release : 2018-12-29
ISBN : 366258395X
Language : En, Es, Fr & De

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Book Description :

This book addresses the experimental calibration of best-estimate numerical simulation models. The results of measurements and computations are never exact. Therefore, knowing only the nominal values of experimentally measured or computed quantities is insufficient for applications, particularly since the respective experimental and computed nominal values seldom coincide. In the author’s view, the objective of predictive modeling is to extract “best estimate” values for model parameters and predicted results, together with “best estimate” uncertainties for these parameters and results. To achieve this goal, predictive modeling combines imprecisely known experimental and computational data, which calls for reasoning on the basis of incomplete, error-rich, and occasionally discrepant information. The customary methods used for data assimilation combine experimental and computational information by minimizing an a priori, user-chosen, “cost functional” (usually a quadratic functional that represents the weighted errors between measured and computed responses). In contrast to these user-influenced methods, the BERRU (Best Estimate Results with Reduced Uncertainties) Predictive Modeling methodology developed by the author relies on the thermodynamics-based maximum entropy principle to eliminate the need for relying on minimizing user-chosen functionals, thus generalizing the “data adjustment” and/or the “4D-VAR” data assimilation procedures used in the geophysical sciences. The BERRU predictive modeling methodology also provides a “model validation metric” which quantifies the consistency (agreement/disagreement) between measurements and computations. This “model validation metric” (or “consistency indicator”) is constructed from parameter covariance matrices, response covariance matrices (measured and computed), and response sensitivities to model parameters. Traditional methods for computing response sensitivities are hampered by the “curse of dimensionality,” which makes them impractical for applications to large-scale systems that involve many imprecisely known parameters. Reducing the computational effort required for precisely calculating the response sensitivities is paramount, and the comprehensive adjoint sensitivity analysis methodology developed by the author shows great promise in this regard, as shown in this book. After discarding inconsistent data (if any) using the consistency indicator, the BERRU predictive modeling methodology provides best-estimate values for predicted parameters and responses along with best-estimate reduced uncertainties (i.e., smaller predicted standard deviations) for the predicted quantities. Applying the BERRU methodology yields optimal, experimentally validated, “best estimate” predictive modeling tools for designing new technologies and facilities, while also improving on existing ones.

Nuclear Systems Volume II

Nuclear Systems Volume II Book
Author : Neil E. Todreas,Mujid S. Kazimi,Mahmoud Massoud
Publisher : CRC Press
Release : 2021-12-13
ISBN : 1482239590
Language : En, Es, Fr & De

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Book Description :

This book provides advanced coverage of a wide variety of thermal fluid systems and technologies in nuclear power plants, including discussions of the latest reactor designs and their thermal/fluid technologies. Beyond the thermal hydraulic design and analysis of the core of a nuclear reactor, the book covers other components of nuclear power plants, such as the pressurizer, containment, and the entire primary coolant system. Placing more emphasis on the appropriate models for small-scale resolution of the velocity and temperature fields through computational fluid mechanics, the book shows how this enhances the accuracy of predicted operating conditions in nuclear plants. It introduces considerations of the laws of scaling and uncertainty analysis, along with a wider coverage of the phenomena encountered during accidents. FEATURES Discusses fundamental ideas for various modeling approaches for the macro- and microscale flow conditions in reactors Covers specific design considerations, such as natural convection and core reliability Enables readers to better understand the importance of safety considerations in thermal engineering and analysis of modern nuclear plants Features end-of-chapter problems Includes a solutions manual for adopting instructors This book serves as a textbook for advanced undergraduate and graduate students taking courses in nuclear engineering and studying thermal/hydraulic systems in nuclear power plants.

Handbook of Nuclear Engineering

Handbook of Nuclear Engineering Book
Author : Dan Gabriel Cacuci
Publisher : Springer Science & Business Media
Release : 2010-09-14
ISBN : 0387981306
Language : En, Es, Fr & De

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Book Description :

This is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all levels, this book provides a condensed reference on nuclear engineering since 1958.

Fundamentals of Nuclear Engineering

Fundamentals of Nuclear Engineering Book
Author : Brent J. Lewis,E. Nihan Onder,Andrew A. Prudil
Publisher : John Wiley & Sons
Release : 2017-03-31
ISBN : 111927155X
Language : En, Es, Fr & De

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Book Description :

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 is missing in traditional texts, such as space radiation. The aim of the book is to provide a source for upper level undergraduate and graduate students studying nuclear engineering.

Nuclear Engineering

Nuclear Engineering Book
Author : Zafar Ullah Koreshi
Publisher : Academic Press
Release : 2022-03-23
ISBN : 0323908314
Language : En, Es, Fr & De

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Book Description :

Nuclear Engineering Mathematical Modeling and Simulation presents the mathematical modeling of neutron diffusion and transport. Aimed at students and early career engineers, this highly practical and visual resource guides the reader through computer simulations using the Monte Carlo Method which can be applied to a variety of applications, including power generation, criticality assemblies, nuclear detection systems, and nuclear medicine to name a few. The book covers optimization in both the traditional deterministic framework of variational methods and the stochastic framework of Monte Carlo methods. Specific sections cover the fundamentals of nuclear physics, computer codes used for neutron and photon radiation transport simulations, applications of analyses and simulations, optimization techniques for both fixed-source and multiplying systems, and various simulations in the medical area where radioisotopes are used in cancer treatment. Provides a highly visual and practical reference that includes mathematical modeling, formulations, models and methods throughout Includes all current major computer codes, such as ANISN, MCNP and MATLAB for user coding and analysis Guides the reader through simulations for the design optimization of both present-day and future nuclear systems

Nuclear Power Plant Design and Analysis Codes

Nuclear Power Plant Design and Analysis Codes Book
Author : Jun Wang,Xin Li,Chris Allison,Judy Hohorst
Publisher : Woodhead Publishing
Release : 2020-11-10
ISBN : 0128181915
Language : En, Es, Fr & De

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Book Description :

Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application presents the latest research on the most widely used nuclear codes and the wealth of successful accomplishments which have been achieved over the past decades by experts in the field. Editors Wang, Li,Allison, and Hohorst and their team of authors provide readers with a comprehensive understanding of nuclear code development and how to apply it to their work and research to make their energy production more flexible, economical, reliable and safe. Written in an accessible and practical way, each chapter considers strengths and limitations, data availability needs, verification and validation methodologies and quality assurance guidelines to develop thorough and robust models and simulation tools both inside and outside a nuclear setting. This book benefits those working in nuclear reactor physics and thermal-hydraulics, as well as those involved in nuclear reactor licensing. It also provides early career researchers with a solid understanding of fundamental knowledge of mainstream nuclear modelling codes, as well as the more experienced engineers seeking advanced information on the best solutions to suit their needs. Captures important research conducted over last few decades by experts and allows new researchers and professionals to learn from the work of their predecessors Presents the most recent updates and developments, including the capabilities, limitations, and future development needs of all codes Incudes applications for each code to ensure readers have complete knowledge to apply to their own setting.

The Second Order Adjoint Sensitivity Analysis Methodology

The Second Order Adjoint Sensitivity Analysis Methodology Book
Author : Dan Gabriel Cacuci
Publisher : CRC Press
Release : 2018-02-19
ISBN : 1498726496
Language : En, Es, Fr & De

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Book Description :

The Second-Order Adjoint Sensitivity Analysis Methodology generalizes the First-Order Theory presented in the author’s previous books published by CRC Press. This breakthrough has many applications in sensitivity and uncertainty analysis, optimization, data assimilation, model calibration, and reducing uncertainties in model predictions. The book has many illustrative examples that will help readers understand the complexity of the subject and will enable them to apply this methodology to problems in their own fields. Highlights: • Covers a wide range of needs, from graduate students to advanced researchers • Provides a text positioned to be the primary reference for high-order sensitivity and uncertainty analysis • Applies to all fields involving numerical modeling, optimization, quantification of sensitivities in direct and inverse problems in the presence of uncertainties. About the Author: Dan Gabriel Cacuci is a South Carolina SmartState Endowed Chair Professor and the Director of the Center for Nuclear Science and Energy, Department of Mechanical Engineering at the University of South Carolina. He has a Ph.D. in Applied Physics, Mechanical and Nuclear Engineering from Columbia University. He is also the recipient of many awards including four honorary doctorates, the Ernest Orlando Lawrence Memorial award from the U.S. Dept. of Energy and the Arthur Holly Compton, Eugene P. Wigner and the Glenn Seaborg Awards from the American Nuclear Society.

Safety and Reliability Methodology and Applications

Safety and Reliability  Methodology and Applications Book
Author : Tomasz Nowakowski,Marek Mlynczak,Anna Jodejko-Pietruczuk,Sylwia Werbinska-Wojciechowska
Publisher : CRC Press
Release : 2014-09-01
ISBN : 1315736977
Language : En, Es, Fr & De

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Book Description :

Within the last fifty years the performance requirements for technical objects and systems were supplemented with: customer expectations (quality), abilities to prevent the loss of the object properties in operation time (reliability and maintainability), protection against the effects of undesirable events (safety and security) and the ability to

Project on Nuclear Issues

Project on Nuclear Issues Book
Author : Mark Cancian
Publisher : Rowman & Littlefield
Release : 2018-03-09
ISBN : 1442280565
Language : En, Es, Fr & De

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Book Description :

The papers in this volume comprise research from participants in the 2017 Nuclear Scholars Initiative and PONI Conference Series. PONI sponsors this research to provide a forum for facilitating new and innovative thinking and a platform for emerging thought leaders across the nuclear enterprise.

Software Engineering for Science

Software Engineering for Science Book
Author : Jeffrey C. Carver,Neil P. Chue Hong,George K. Thiruvathukal
Publisher : CRC Press
Release : 2016-11-03
ISBN : 1498743862
Language : En, Es, Fr & De

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Book Description :

Software Engineering for Science provides an in-depth collection of peer-reviewed chapters that describe experiences with applying software engineering practices to the development of scientific software. It provides a better understanding of how software engineering is and should be practiced, and which software engineering practices are effective for scientific software. The book starts with a detailed overview of the Scientific Software Lifecycle, and a general overview of the scientific software development process. It highlights key issues commonly arising during scientific software development, as well as solutions to these problems. The second part of the book provides examples of the use of testing in scientific software development, including key issues and challenges. The chapters then describe solutions and case studies aimed at applying testing to scientific software development efforts. The final part of the book provides examples of applying software engineering techniques to scientific software, including not only computational modeling, but also software for data management and analysis. The authors describe their experiences and lessons learned from developing complex scientific software in different domains. About the Editors Jeffrey Carver is an Associate Professor in the Department of Computer Science at the University of Alabama. He is one of the primary organizers of the workshop series on Software Engineering for Science (http://www.SE4Science.org/workshops). Neil P. Chue Hong is Director of the Software Sustainability Institute at the University of Edinburgh. His research interests include barriers and incentives in research software ecosystems and the role of software as a research object. George K. Thiruvathukal is Professor of Computer Science at Loyola University Chicago and Visiting Faculty at Argonne National Laboratory. His current research is focused on software metrics in open source mathematical and scientific software.

Memory Efficient Indexing Algorithm for Physical Properties in OpenMC

Memory Efficient Indexing Algorithm for Physical Properties in OpenMC Book
Author : Derek Michael Lax
Publisher : Unknown
Release : 2015
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Book Description :

OpenMC is an open source Monte Carlo code designed at MIT with a focus on parallel scalability for large nuclear reactor simulations. The target problem for OpenMC is a full core high-fidelity multi-physics coupled simulation. This encompasses not only nuclear physics, but also material science and thermohydraulics. One of the challenges associated with this problem is efficient data management, as the memory required for tallies alone can easily enter the Terabyte range. This thesis presents an efficient system for data storage which allows for physical properties of materials to be indexed without any constraints on the geometry. To demonstrate its functionality, a sample depletion calculation with 4 isotopes is completed on the BEAVRS benchmark geometry. Additionally, a temperature distribution assembly layout is presented.

Nuclear Reactors

Nuclear Reactors Book
Author : Chad L. Pope
Publisher : BoD – Books on Demand
Release : 2022-09-14
ISBN : 1839699396
Language : En, Es, Fr & De

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Book Description :

Worldwide interest in nuclear reactors continues to increase and significant focus has been placed on advanced nuclear reactors intended to produce electricity and process heat. However, there is limited literature on the importance of research reactors and certain specialized reactor analysis topics. Thus, this book addresses these topics over three sections: “Nuclear Reactors for Spacecraft Propulsion”, “Research Reactors”, and “Select Reactor Analysis Techniques”. It provides detailed information on the use of nuclear reactors for spacecraft propulsion, presents research conducted on reactors in Idaho, USA, and discusses reactor analysis topics such as cyber-informed engineering for nuclear reactor digital instrumentation and control, the effect of plenum gas on fuel temperature, and more.

Methods for Including Multiphysics Feedback in Monte Carlo Reactor Physics Calculations

Methods for Including Multiphysics Feedback in Monte Carlo Reactor Physics Calculations Book
Author : Matthew Shawn Ellis
Publisher : Unknown
Release : 2017
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Book Description :

The ability to model and simulate nuclear reactors during steady state and transient conditions is important for designing efficient and safe nuclear power systems. The accurate simulation of a nuclear reactor is particularly challenging because the multiple physical processes within the reactor are tightly coupled, which requires that the numerical methods used to resolve each physical process can accurately and efficiently transfer and utilize data from other applications. Monte Carlo methods are desirable for solving the neutron transport equation required in reactor analysis because of the inherent accuracy of the method, but the Computational Solid Geometry (CSG) representation of the physical geometry makes it difficult to accurately and efficiently perform multiphysics reactor analyses with other applications that utilize finite element or finite volume representations. To address this limitation, a multiphysics coupling framework that minimizes the need for spatial discretization in the Monte Carlo geometry is presented in this thesis. The coupling framework uses Functional Expansion Tallies to transfer multiphysics information from the Monte Carlo application to other multiphysics tools. Additionally, the coupling framework uses a modified method for transporting neutrons through spatially continuous total macroscopic cross section distributions in order to incorporate continuous multiphysics feedback fields such as fuel temperature and coolant density into the Monte Carlo simulation. It has been shown that separable Zernike and Legendre Function Expansion Tallies can effectively reconstruct a continuous distribution of fission power density. Additionally, using a prototypical three-dimensional Light Water Reactor pin cell, the method used to transport neutrons through a continuously varying fuel temperature and coolant density distribution was shown to be 1.7 times faster than a comparable discretized simulation with volume-averaged properties, while still providing a high level of accuracy. Finally, in order to make the overall multiphysics coupling scheme useful for reactor analyses, a novel spatially continuous depletion methodology was developed and investigated. With the spatially continuous depletion methodology, number densities can be represented as a linear combination of polynomials, and those polynomial representations can be integrated through time to predict reactor operation. The spatially continuous depletion methodology was able to accurately predict the eigenvalue and number density distributions in a two-dimensional LWR pin cell depletion containing Gd-157 from a 2 weight percent GdO2 and seven other nuclides in the depletion matrix. Analyses of the spatially continuous depletion methodology showed that significant reductions in the number of tallied values could be achieved if polynomial representations were optimized for each nuclide reaction rate. From the depletion simulations in this thesis, a 23% reduction in the required number of reaction rate tallies compared to a lower-fidelity, 10 radial ring pin discretization was shown to be achievable with nuclide polynomial optimization. In addition to showing potential for reductions in tally memory and computational requirements, the spatially continuous depletion simulation was shown to be equal in computational performance to a discrete simulation with 10 radial rings and 8 azimuthal cuts, while providing a much higher level of spatial fidelity in number density concentrations.