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
Publsiher: Woodhead Publishing
Total Pages: 700
Release: 2019-06-15
ISBN 10: 0081023375
ISBN 13: 9780081023372
Language: EN, FR, DE, ES & NL

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

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 practice, and the future of CFD in nuclear reactors. Readers will find a thematic discussion on each aspect of CFD applications for the design and safety assessment of Gen II to Gen IV reactor concepts that will help them develop cost reduction strategies for nuclear power plants. Presents a thematic and comprehensive discussion on each aspect of CFD applications for the design and safety assessment of nuclear reactors Provides an historical review of the development of CFD models, discusses state-of-the-art concepts, and takes an applied and analytic look toward the future Includes CFD tools and simulations to advise and guide the reader through enhancing cost effectiveness, safety and performance optimization

Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors
Author: Ferry Roelofs
Publsiher: Woodhead Publishing
Total Pages: 462
Release: 2018-11-30
ISBN 10: 0081019815
ISBN 13: 9780081019818
Language: EN, FR, DE, ES & NL

Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors Book Review:

Thermal Hydraulics Aspects of Liquid Metal cooled Nuclear Reactors is a comprehensive collection of liquid metal thermal hydraulics research and development for nuclear liquid metal reactor applications. A deliverable of the SESAME H2020 project, this book is written by top European experts who discuss topics of note that are supplemented by an international contribution from U.S. partners within the framework of the NEAMS program under the U.S. DOE. This book is a convenient source for students, professionals and academics interested in liquid metal thermal hydraulics in nuclear applications. In addition, it will also help newcomers become familiar with current techniques and knowledge. Presents the latest information on one of the deliverables of the SESAME H2020 project Provides an overview on the design and history of liquid metal cooled fast reactors worldwide Describes the challenges in thermal hydraulics related to the design and safety analysis of liquid metal cooled fast reactors Includes the codes, methods, correlations, guidelines and limitations for liquid metal fast reactor thermal hydraulic simulations clearly Discusses state-of-the-art, multi-scale techniques for liquid metal fast reactor thermal hydraulics applications

Energy Research Abstracts

Energy Research Abstracts
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 1993
ISBN 10: 1928374650XXX
ISBN 13: MINN:30000006337277
Language: EN, FR, DE, ES & NL

Energy Research Abstracts Book Review:

Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.

Computational Fluid Structure Interaction for Nuclear Reactor Applications

Computational Fluid Structure Interaction for Nuclear Reactor Applications
Author: Afaque Shams
Publsiher: Woodhead Publishing
Total Pages: 300
Release: 2022-06-15
ISBN 10: 9780128228098
ISBN 13: 0128228091
Language: EN, FR, DE, ES & NL

Computational Fluid Structure Interaction for Nuclear Reactor Applications Book Review:

Computational Fluid-Structure Interaction for Nuclear Reactor Applications presents the latest knowledge on the use of Computational Fluid Dynamics (CFD) and Computational Structural Dynamic (CSM) tools to solve Fluid-Structure Interaction (FSI) problems in a nuclear setting. Editor Dr Afaque Shams and his team of expert contributors from around the globe provide a detailed background on the topic as well as a comprehensive picture of recent developments of computational FSI in a variety of nuclear reactors. Mechanical damages which threaten the integrity and safety of nuclear plants need to be mitigated at the design stage, and this book provides a clear understanding of FSI issues such as vibration, noise, wear and fatigue which will work to reduce accident vulnerabilities in the long run. Numerical algorithms, modelling and applications, validation and verification approaches are included to equip nuclear professionals, plant designers and analysists, and researchers with a solid understanding of the state-of-the-art approaches for FSI and its advanced applications and modern approaches. Includes numerical methods, modelling, validation and verification of all approaches presented Provides best practice guidelines to perform FSI simulations for various nuclear reactor applications Reviews the present status of tools to perform FSI computations and provides future perspectives for further research opportunities

Monthly Catalog of United States Government Publications

Monthly Catalog of United States Government Publications
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 1982
ISBN 10: 1928374650XXX
ISBN 13: WISC:89117116806
Language: EN, FR, DE, ES & NL

Monthly Catalog of United States Government Publications Book Review:

Strategic Plan for Nuclear Energy Knowledge Base for Advanced Modeling and Simulation NE KAMS

Strategic Plan for Nuclear Energy    Knowledge Base for Advanced Modeling and Simulation  NE KAMS
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 2011
ISBN 10: 1928374650XXX
ISBN 13: OCLC:1065672800
Language: EN, FR, DE, ES & NL

Strategic Plan for Nuclear Energy Knowledge Base for Advanced Modeling and Simulation NE KAMS Book Review:

The Nuclear Energy Computational Fluid Dynamics Advanced Modeling and Simulation (NE-CAMS) system is being developed at the Idaho National Laboratory (INL) in collaboration with Bettis Laboratory, Sandia National Laboratory (SNL), Argonne National Laboratory (ANL), Utah State University (USU), and other interested parties with the objective of developing and implementing a comprehensive and readily accessible data and information management system for computational fluid dynamics (CFD) verification and validation (V & V) in support of nuclear energy systems design and safety analysis. The two key objectives of the NE-CAMS effort are to identify, collect, assess, store and maintain high resolution and high quality experimental data and related expert knowledge (metadata) for use in CFD V & V assessments specific to the nuclear energy field and to establish a working relationship with the U.S. Nuclear Regulatory Commission (NRC) to develop a CFD V & V database, including benchmark cases, that addresses and supports the associated NRC regulations and policies on the use of CFD analysis. In particular, the NE-CAMS system will support the Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program, which aims to develop and deploy advanced modeling and simulation methods and computational tools for reliable numerical simulation of nuclear reactor systems for design and safety analysis. Primary NE-CAMS Elements There are four primary elements of the NE-CAMS knowledge base designed to support computer modeling and simulation in the nuclear energy arena as listed below. Element 1. The database will contain experimental data that can be used for CFD validation that is relevant to nuclear reactor and plant processes, particularly those important to the nuclear industry and the NRC. Element 2. Qualification standards for data evaluation and classification will be incorporated and applied such that validation data sets will result in well-defined, well-characterized data. Element 3. Standards will be established for the design and operation of experiments for the generation of new validation data sets that are to be submitted to NE-CAMS that addresses the completeness and characterization of the dataset. Element 4. Standards will be developed for performing verification and validation (V & V) to establish confidence levels in CFD analyses of nuclear reactor processes; such processes will be acceptable and recognized by both CFD experts and the NRC.

International Atomic Energy Agency Publications

International Atomic Energy Agency Publications
Author: International Atomic Energy Agency
Publsiher: Unknown
Total Pages: 135
Release: 2004
ISBN 10: 1928374650XXX
ISBN 13: STANFORD:36105133465935
Language: EN, FR, DE, ES & NL

International Atomic Energy Agency Publications Book Review:

ERDA Energy Research Abstracts

ERDA Energy Research Abstracts
Author: United States. Energy Research and Development Administration
Publsiher: Unknown
Total Pages: 135
Release: 1976
ISBN 10: 1928374650XXX
ISBN 13: UOM:39015048721255
Language: EN, FR, DE, ES & NL

ERDA Energy Research Abstracts Book Review:

Nuclear News

Nuclear News
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 1996
ISBN 10: 1928374650XXX
ISBN 13: UCSD:31822023347347
Language: EN, FR, DE, ES & NL

Nuclear News Book Review:

Computational Fluid Dynamics CFD of Chemical Processes

Computational Fluid Dynamics  CFD  of Chemical Processes
Author: Young-Il Lim
Publsiher: MDPI
Total Pages: 114
Release: 2021-02-22
ISBN 10: 3039439332
ISBN 13: 9783039439331
Language: EN, FR, DE, ES & NL

Computational Fluid Dynamics CFD of Chemical Processes Book Review:

In this Special Issue, one review paper highlights the necessity of multiscale CFD, coupling micro- and macro-scales, for exchanging information at the interface of the two scales. Four research papers investigate the hydrodynamics, heat transfer, and chemical reactions of various processes using Eulerian CFD modeling. CFD models are attractive for industrial applications. However, substantial efforts in physical modeling and numerical implementation are still required before their widespread implementation.

Argonne Liquid Metal Advanced Burner Reactor

Argonne Liquid Metal Advanced Burner Reactor
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 2007
ISBN 10: 1928374650XXX
ISBN 13: OCLC:727351964
Language: EN, FR, DE, ES & NL

Argonne Liquid Metal Advanced Burner Reactor Book Review:

This white paper provides an overview and status report of the thermal-hydraulic nuclear research and development, both experimental and computational, conducted predominantly at Argonne National Laboratory. Argonne from the early 1970s through the early 1990s was the Department of Energy's (DOE's) lead lab for thermal-hydraulic development of Liquid Metal Reactors (LMRs). During the 1970s and into the mid-1980s, Argonne conducted thermal-hydraulic studies and experiments on individual reactor components supporting the Experimental Breeder Reactor-II (EBR-II), Fast Flux Test Facility (FFTF), and the Clinch River Breeder Reactor (CRBR). From the mid-1980s and into the early 1990s, Argonne conducted studies on phenomena related to forced- and natural-convection thermal buoyancy in complete in-vessel models of the General Electric (GE) Prototype Reactor Inherently Safe Module (PRISM) and Rockwell International (RI) Sodium Advanced Fast Reactor (SAFR). These two reactor initiatives involved Argonne working closely with U.S. industry and DOE. This paper describes the very important impact of thermal hydraulics dominated by thermal buoyancy forces on reactor global operation and on the behavior/performance of individual components during postulated off-normal accident events with low flow. Utilizing Argonne's LMR expertise and design knowledge is vital to the further development of safe, reliable, and high-performance LMRs. Argonne believes there remains an important need for continued research and development on thermal-hydraulic design in support of DOE's and the international community's renewed thrust for developing and demonstrating the Global Nuclear Energy Partnership (GNEP) reactor(s) and the associated Argonne Liquid Metal-Advanced Burner Reactor (LM-ABR). This white paper highlights that further understanding is needed regarding reactor design under coolant low-flow events. These safety-related events are associated with the transition from normal high-flow operation to natural circulation. Low-flow coolant events are the most difficult to design for because they involve the most complex thermal-hydraulic behavior induced by the dominance of thermal-buoyancy forces acting on the coolants. Such behavior can cause multiple-component flow interaction phenomena, which are not adequately understood or appreciated by reactor designers as to their impact on reactor performance and safety. Since the early 1990s, when DOE canceled the U.S. Liquid Metal Fast Breeder Reactor (LMFBR) program, little has been done experimentally to further understand the importance of the complex thermal-buoyancy phenomena and their impact on reactor design or to improve the ability of three-dimensional (3-D) transient computational fluid dynamics (CFD) and structures codes to model the phenomena. An improved experimental data base and the associated improved validated codes would provide needed design tools to the reactor community. The improved codes would also facilitate scale-up from small-scale testing to prototype size and would facilitate comparing performance of one reactor/component design with another. The codes would also have relevance to the design and safety of water-cooled reactors. To accomplish the preceding, it is proposed to establish a national GNEP-LMR research and development center at Argonne having as its foundation state-of-art science-based infrastructure consisting of: (a) thermal-hydraulic experimental capabilities for conducting both water and sodium testing of individual reactor components and complete reactor in-vessel models and (b) a computational modeling development and validation capability that is strongly interfaced with the experimental facilities. The proposed center would greatly advance capabilities for reactor development by establishing the validity of high-fidelity (i.e., close to first principles) models and tools. Such tools could be used directly for reactor design or for qualifying/tuning of lower-fidelity models, which now require costly experimental qualification for each different type of design application. Capabilities required to establish and operate this center are found primarily in Argonne's Nuclear Engineering and Mathematics and Computer Science Divisions. Funding for the center would be sought from DOE-NE (GNEP/Advanced Burner Reactor and Generation IV programs), DOE-SC/ASCR, and the commercial nuclear industry. Having the above experimental and modeling capabilities at Argonne would constitute a national/international center of excellence for conducting the research and engineering and design tool development needed to support the DOE GNEP/ LM-ABR initiative in developing safe, high-performance reactors.

The Agency s Programme and Budget for

The Agency s Programme and Budget for
Author: International Atomic Energy Agency
Publsiher: Unknown
Total Pages: 135
Release: 2006
ISBN 10: 1928374650XXX
ISBN 13: MINN:31951D024727790
Language: EN, FR, DE, ES & NL

The Agency s Programme and Budget for Book Review:

The Agency s Budget Update for

The Agency s Budget Update for
Author: International Atomic Energy Agency
Publsiher: Unknown
Total Pages: 135
Release: 2006
ISBN 10: 1928374650XXX
ISBN 13: UOM:39015058774673
Language: EN, FR, DE, ES & NL

The Agency s Budget Update for Book Review:

Modelling of Nuclear Reactor Multi physics

Modelling of Nuclear Reactor Multi physics
Author: Christophe Demazière
Publsiher: Academic Press
Total Pages: 368
Release: 2019-11-19
ISBN 10: 012815070X
ISBN 13: 9780128150702
Language: EN, FR, DE, ES & NL

Modelling of Nuclear Reactor Multi physics Book Review:

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

Transactions of the American Nuclear Society

Transactions of the American Nuclear Society
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 2001
ISBN 10: 1928374650XXX
ISBN 13: UOM:39015047953933
Language: EN, FR, DE, ES & NL

Transactions of the American Nuclear Society Book Review:

Annual Report

Annual Report
Author: OECD Nuclear Energy Agency
Publsiher: Unknown
Total Pages: 135
Release: 2003
ISBN 10: 1928374650XXX
ISBN 13: WISC:89098405954
Language: EN, FR, DE, ES & NL

Annual Report Book Review:

Revue G n rale Nucl aire

Revue G  n  rale Nucl  aire
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 2000
ISBN 10: 1928374650XXX
ISBN 13: UCSD:31822022910418
Language: EN, FR, DE, ES & NL

Revue G n rale Nucl aire Book Review:

Nuclear Technology

Nuclear Technology
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 1990
ISBN 10: 1928374650XXX
ISBN 13: UCSD:31822005492350
Language: EN, FR, DE, ES & NL

Nuclear Technology Book Review:

Circular

Circular
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 1966
ISBN 10: 1928374650XXX
ISBN 13: CORNELL:31924077925240
Language: EN, FR, DE, ES & NL

Circular Book Review:

Government Reports Announcements Index

Government Reports Announcements   Index
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 1996
ISBN 10: 1928374650XXX
ISBN 13: PSU:000047869172
Language: EN, FR, DE, ES & NL

Government Reports Announcements Index Book Review: