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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 : 09 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

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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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Use of Computational Fluid Dynamics Codes for Safety Analysis of Nuclear Reactor Systems

With further progress in safety analysis techniques, the increasing use of three dimensional computational fluid dynamics (CFD) codes for nuclear applications is expected. The present publication constitutes the report of the joint IAEA and OECD/NEA technical meeting on the Use of CFD Codes for Safety Analysis of Reactor Systems, including Containment, held in Pisa, Italy, from 11 to 14 November 2002. It includes summaries of the presentations and of the discussions as well as conclusions and recommendations for further work. A CD

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Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors
  • Author : Ferry Roelofs
  • Publisher : Woodhead Publishing
  • Release : 30 November 2018
GET THIS BOOKThermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

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

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Computational Fluid-Structure Interaction for Nuclear Reactor Applications

Computational Fluid-Structure Interaction for Nuclear Reactor Applications
  • Author : Afaque Shams
  • Publisher : Woodhead Publishing
  • Release : 15 June 2022
GET THIS BOOKComputational Fluid-Structure Interaction for Nuclear Reactor Applications

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

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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

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Nuclear Power Plant Design and Analysis Codes

Nuclear Power Plant Design and Analysis Codes
  • Author : Jun Wang,Xin Li,Chris Allison,Judy Hohorst
  • Publisher : Woodhead Publishing
  • Release : 10 November 2020
GET THIS BOOKNuclear Power Plant Design and Analysis Codes

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,

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Argonne Liquid-Metal Advanced Burner Reactor

Argonne Liquid-Metal Advanced Burner Reactor
  • Author : Anonim
  • Publisher : Anonim
  • Release : 04 December 2021
GET THIS BOOKArgonne Liquid-Metal Advanced Burner Reactor

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),

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Computational Fluid Dynamics (CFD) of Chemical Processes

Computational Fluid Dynamics (CFD) of Chemical Processes
  • Author : Young-Il Lim
  • Publisher : MDPI
  • Release : 22 February 2021
GET THIS BOOKComputational Fluid Dynamics (CFD) of Chemical Processes

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.

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Design-basis Accident Analysis Methods For Light-water Nuclear Power Plants

Design-basis Accident Analysis Methods For Light-water Nuclear Power Plants
  • Author : Robert Martin,Cesare Frepoli
  • Publisher : World Scientific
  • Release : 13 February 2019
GET THIS BOOKDesign-basis Accident Analysis Methods For Light-water Nuclear Power Plants

This book captures the principles of safety evaluation as practiced in the regulated light-water reactor nuclear industry, as established and stabilized over the last 30 years. It is expected to serve both the current industry and those planning for the future. The work's coverage of the subject matter is the broadest to date, including not only the common topics of modeling and simulation, but also methods supporting the basis for the underlying assumptions, the extension to radiological safety, what to expect

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

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

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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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Progress of Nuclear Safety for Symbiosis and Sustainability

Progress of Nuclear Safety for Symbiosis and Sustainability
  • Author : Hidekazu Yoshikawa,Zhijian Zhang
  • Publisher : Springer Science & Business Media
  • Release : 20 March 2014
GET THIS BOOKProgress of Nuclear Safety for Symbiosis and Sustainability

This book introduces advanced methods of computational and information systems allowing readers to better understand the state-of-the-art design and implementation technology needed to maintain and enhance the safe operation of nuclear power plants. The subjects dealt with in the book are (i) Full digital instrumentation and control systems and human–machine interface technologies (ii) Risk monitoring methods for large and complex plants (iii) Condition monitors for plant components (iv) Virtual and augmented reality for nuclear power plants and (v) Software

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