Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment - 1st Edition - ISBN: 9780081023372

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

1st Edition

Editors: Jyeshtharaj Joshi Arun Nayak
Paperback ISBN: 9780081023372
Imprint: Woodhead Publishing
Published Date: 1st June 2019
Page Count: 700
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Table of Contents

1. Introduction: Nuclear Reactor Safety Issues
By A.K. Nayak
1.1 Nuclear Power Development – A Historical Review
1.2 Design of Nuclear Reactors for Safety
1.3 Quantification of Safety Margins
1.4 Role of CFD
1.5 Closure
1.6 References
2. CFD – Present State of the Art
By J.B. Joshi
2.1 Introduction
2.2 Evolving trends in process design from ancient
to modern times
2.3 Key design parameters for reaction and flow processes
in multiphase reactors
2.3.1 Understanding and Modeling Intrinsic Reaction Rate Mechanisms
2.3.2 Classification of Multiphase Reactors
2.3.3 Fluid Mechanical Parameters and Their Relationship with Design Objectives

2.4 Generalized high-fidelity Modeling Framework That Will Shape Future Reactor Designs
2.4.1 Insights from Molecular Dynamics
2.4.2 High-Fidelity Continuum-Scale Models
2.4.3 Computational Fluid Dynamics: Single-Phase Laminar
and Turbulent Flow Models
2.4.4 Computational Fluid Dynamics: Two-Fluid Models
For Coarse-Grained Flow Structures
2.4.5 Computational Fluid Dynamics: Discrete Particle Model:
For Flow Structure–Solids Interactions
2.4.6 Computational Fluid Dynamics: Population Balance Models: For Flow Structure–Bubble Interactions
2.4.7 Computational Fluid Dynamics: Population Balance Models: For Flow Structure–Bubble Interactions CFD–DNS: hydrodynamics of fluid-particle systems CFD–DNS: particle-turbulent interactions/modulations CFD–DNS: Drag,Lift, and Vrtual Mass CFD–DNS: Heat and Mass Transport in Fluid-Particle Systems
2.4.8 Application of Direct Numerical Simulations in Determining perimeter in Low-Order Models
2.5 Computational Fluid Dynamics Framework to Enable Innovations in Multiphase Reactor Design
2.6 Conclusions and Suggestions for Future Work
2.7 Literature Cited
3.  Evaluation of Safety of Water Cooled Reactors using CFD
     3.1 Phenomenological Issues of Reactor Safety in Accidents
     3.2 Application of CFD Codes in Nuclear Reactor Safety Analysis
     3.3 Advances in CFD for rod-bundle thermal hydraulics during normal operation and LOCA
     3.5 Simulation of moderator of flow field and poison distribution in HWRs using CFD
     3.6 Containment thermal hydraulics simulation in LOCA – application of CFD and limitations
     3.7 CFD simulation of Hydrogen distribution in Containment
     3.9 Modelling of fire using CFD
     3.10 Modelling of Fluid Structure Interactions
     3.11 Closure
     3.12 References
4.  Design of Passive Safety Systems for Advanced Reactors Using CFD
     4.1 Introduction to Passive Safety Systems
     4.2 Requirement of CFD for Passive Safety System Design
    4.3 Design of Passive Residual Heat Removal Systems Using CFD
    4.4 Design of Passive Moderator Cooling System using CFD
    4.5 Design of Passive Air Cooled Heat Exchangers Using CFD
    4.5 Design of Passive Venturi Scrubber System Using CFD
    4.6 Design of a Steam Drum for Gravity Separation Using CFD
    4.7 CFD application for PARs Design
    4.8 CFD application for design of Suppression Pool With Elimination of Thermal Stratification
    4.9 Modelling Natural Convection Phenomena Using CFD – Issues and Challenges
    4.10 Closure
    4.11 References
5. Modelling of Severe Accident Phenomena Using CFD
    5.1 Introduction to Severe Accident Phenomena and Progression in Water Cooled Reactors
    5.2 Current Status of Application of CFD codes for Severe Accident
    5.3 Modelling of Debris Coolability Using CFD
    5.4 Simulation of In-calandria retention of corium in PHWRs Using CFD
    5.5 Development of Core Catcher – Simulation of Ablation of Sacrificial Material Using CFD
    5.6 Molten fuel coolant interaction – CFD Simulation Studies
    5.7 Prediction of fission product transport using CFD
    5.8 CFD Simulation of Hydrogen Deflagration and Detonation
    5.9 Atmospheric transport of aerosols
    5.10 Closure
    5.11 References
6. CFD Model Development for Two-phase Flows
    6.1 Importance of Two-phase flow Modelling in nuclear reactors
    6.2 Modelling Two-phase adiabatic flow using CFD – current status
    6.3 CFD modelling of boiling phenomena
    6.4 CFD modelling of condensation
    6.5 BWR rod bundle flow distribution – applicability of CFD modules
    6.7 Modelling bubble dynamics in suppression pool Using CFD
    6.8 Modelling of Critical Heat Flux in BWRs Using CFD
    6.9 Closure
    6.10 References
7. CFD Application for Sodium and Molten Salt Reactor Designs
     7.1 Thermal hydraulic issues in Sodium Cooled Reactors requiring CFD Simulation
     7.2 Thermal hydraulic issues in Molten salt Reactors requiting CFD Simulation
     7.3 Simulation of flow behaviour in sodium pool in Indian Fast Reactors
     7.4 Simulation of flow behaviour in molten salt natural circulation systems using CFD codes
     7.5 CFD simulation of Sodium Fire Studies
     7.6 CFD simulation of thermal stripping in fast reactor
     7.7 Closure
     7.8 References
8. CFD Development – Future Development and Strategies
     8.1 Current limitations of CFD tools
     8.2 Validation Issues and Challenges
     8.3 CFD – New models development requirement addressing important issues
     8.4 Strategies for the new models development
     8.5 Closure
     8.6 References


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.

Key Features

  • 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


Engineers, scientists, researchers and academics working in all aspects of nuclear reactors, especially their design and analysis of their safety; nuclear plant designers and managers; nuclear reactor designers, safety specialists, regulators and all professionals working in CFD


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© Woodhead Publishing 2019
Woodhead Publishing
Paperback ISBN:

Ratings and Reviews

About the Editors

Jyeshtharaj Joshi Editor

Jyeshtharaj Bhalchandra Joshi is an Indian chemical engineer, nuclear scientist, consultant and teacher, widely known for his innovations in nuclear reactor designs and generally regarded as a respected teacher. He is the DAE-Homi Bhabha Chair Professor, Homi Bhabha National Institute, Mumbai, J. C. Bose Fellow of the Institute of Chemical Technology, Mumbai and is the recipient of Shantiswarup Bhatnagar Prize for Engineering Sciences and many other awards and recognitions. He received the third highest civilian honour, the Padma Bhushan, in 2014, from the President of India, for his services to the field of chemical engineering and nuclear science. He is widely published in many journals including the International Journal of Heat and Mass Transfer, Progress in Nuclear Energy, Chemical Engineering Science and Nuclear Engineering and Design

Affiliations and Expertise

Emeritus Professor, Department of Atomic Energy, Mumbai, India

Arun Nayak Editor

Dr. Nayak received his PhD from TITech, Japan in 2000 in Nuclear Engineering, and his field of Specialization is Nuclear Reactor Thermalhydraulics and Safety. He has received multiple awards, prizes and honorary degrees throughout his career and is a life member of the Indian Nuclear Society and Indian Society of Heat and Mass Transfer. He has published over 73 peer reviewed articles and 140 conference proceedings.

Affiliations and Expertise

Scientific Officer and Head, Thermal Hydraulics Section of Bhabha Atomic Research Centre and Professor, Hombi Bhabha National Institute, Mumbai, India