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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
  • Publsiher : Woodhead Publishing
  • Release : 15 June 2019
  • ISBN : 0081023375
  • Pages : 700 pages
  • Rating : 4/5 from 21 ratings
GET THIS BOOKAdvances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment

Summary:
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


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

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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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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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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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Argonne Liquid-Metal Advanced Burner Reactor

Argonne Liquid-Metal Advanced Burner Reactor
  • Author : Anonim
  • Publisher : Anonim
  • Release : 16 May 2022
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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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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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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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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Thermal-Hydraulic Analysis of Nuclear Reactors

Thermal-Hydraulic Analysis of Nuclear Reactors
  • Author : Bahman Zohuri
  • Publisher : Springer
  • Release : 23 May 2017
GET THIS BOOKThermal-Hydraulic Analysis of Nuclear Reactors

This revised text covers the fundamentals of thermodynamics required to understand electrical power generation systems and the application of these principles to nuclear reactor power plant systems. The book begins with fundamental definitions of units and dimensions, thermodynamic variables and the Laws of Thermodynamics progressing to sections on specific applications of the Brayton and Rankine cycles for power generation and projected reactor systems design issues. It is not a traditional general thermodynamics text, per se, but a practical thermodynamics volume

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