Advances 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 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

Produk Detail:

  • Author : Jyeshtharaj Joshi
  • Publisher : Woodhead Publishing
  • Pages : 700 pages
  • ISBN : 0081023375
  • Rating : 4/5 from 21 reviews
CLICK HERE TO 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

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

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

Severe Accidents in Nuclear Reactors

Severe Accidents in Nuclear Reactors
  • Author : Arun K. Nayak,Parimal Pramod Kulkarni
  • Publisher : Woodhead Publishing
  • Release : 02 August 2021
GET THIS BOOKSevere Accidents in Nuclear Reactors

Severe Accidents in Nuclear Reactors: Corium Retention Technologies and Insights presents an authoritative and practical analysis of the latest severe accident management strategies based on previous events and experiments. Written for utilities and industries operating and researching nuclear cooled reactor power plants, this book presents the exponential growth in research since major nuclear accidents and acts as a guide to retaining molten corium, both inside and outside the reactor vessel. Sections cover the physics behind several complex phenomena occurring during

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

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

Use of Computational Fluid Dynamics Codes for Safety Analysis of Nuclear Reactor Systems
  • Author : Anonim
  • Publisher : Unknown Publisher
  • Release : 09 December 2021
GET THIS BOOKUse 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

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

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

Proceedings of The 20th Pacific Basin Nuclear Conference

Proceedings of The 20th Pacific Basin Nuclear Conference
  • Author : Hong Jiang
  • Publisher : Springer
  • Release : 10 January 2017
GET THIS BOOKProceedings of The 20th Pacific Basin Nuclear Conference

This is the first in a series of three proceedings of the 20th Pacific Basin Nuclear Conference (PBNC). This volume covers the topics of Safety and Security, Public Acceptance and Nuclear Education, as well as Economics and Reducing Cost. As one in the most important and influential conference series of nuclear science and technology, the 20th PBNC was held in Beijing and the theme of this meeting was “Nuclear: Powering the Development of the Pacific Basin and the World”. It

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,

Argonne Liquid-Metal Advanced Burner Reactor

Argonne Liquid-Metal Advanced Burner Reactor
  • Author : Anonim
  • Publisher : Unknown Publisher
  • Release : 09 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),

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