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E-grāmata: Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment

Edited by (Outstanding Scientist and Head, Thermal Hydraulics Section of Bhabha Atomic Research Centre
Professor, Hombi Bhabha National Institute, Mumbai, India), Edited by (Emeritus Professor, Department of Atomic Energy, Mumbai, India)
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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
Contributors xi
Preface xv
Foreword xvii
1 Introduction
1(20)
Arun K. Nayak
1.1 History of development of nuclear reactors
1(1)
1.2 Notable early nuclear reactors
1(4)
1.3 Growth of nuclear power
5(1)
1.4 Physics of nuclear safety
6(3)
1.5 Designing for safety of nuclear reactors
9(2)
1.6 Quantification of safety margins
11(3)
1.7 Role of CFD in safety assessment
14(3)
1.8 Closure
17(4)
References
19(2)
2 Computational fluid dynamics
21(218)
Jyeshtharaj B. Joshi
Krishnaswamy Nandakumar
Ashwin W. Patwardhan
Arun K. Nayak
Vishnu Pareek
Monica Gumulya
Chunliang Wu
Nitin Minocha
Eshita Pal
Mukesh Kumar
Vishal Bhusare
Shashank Tiwari
Dhiraj Lote
Chaitanya Mali
Ameya Kulkarni
Sarang Tamhankar
2.1 Introduction
30(4)
2.2 Single-phase flow: Model equations
34(8)
2.3 Turbulence models for single-phase flows
42(48)
2.4 CFD modeling of multiphase flows
90(55)
2.5 Models for dense particulate flows
145(20)
2.6 Algorithms
165(74)
References
218(20)
Further reading
238(1)
3 CFD model development for two-phase flows
239(98)
Marco Colombo
M. Fairweather
Simon P. Walker
Mukesh Kumar
Avinash Moharana
Arun K. Nayak
Jyeshtharaj B. Joshi
Arnab Dasgupta
Dinesh K. Chandraker
Tanskanen Vesa
Patel Giteshkumar
3.1 CFD analysis and prediction of boiling flows
242(20)
3.2 CFD modelling of boiling flows inside rod bundle
262(23)
3.3 Modelling of critical heat flux in BWRs: Role of CFD
285(17)
3.4 Modelling bubble dynamics in suppression pool using CFD
302(35)
Acknowledgements
323(1)
References
324(11)
Further reading
335(2)
4 Evaluation of safety of light-water-cooled reactors using CFD
337(50)
Thomas Hohne
4.1 Introduction
337(1)
4.2 Coolant mixing
337(18)
4.3 CFD simulations for horizontal stratified two-phase flows
355(20)
4.4 Capability of CFD codes
375(1)
4.5 Conclusion
375(12)
Acknowledgment
375(1)
Annex
376(8)
References
384(2)
Further reading
386(1)
5 Design of passive safety systems for advanced reactors using CFD
387(100)
Jyeshtharaj B. Joshi
Arun K. Nayak
Nitin Minocha
Eshita Pal
Ankur Kumar
Mukesh Kumar
Avinash Moharana
5.1 Introduction to passive safety systems
390(3)
5.2 CFD requirement for simulation of passive systems
393(1)
5.3 Modeling of natural convection phenomena using CFD---Issues and challenges
394(7)
5.4 Design of passive residual heat removal system (PRHRS) using CFD
401(27)
5.5 Design of passive moderator cooling system using CFD
428(22)
5.6 Design of passive air-cooled condensers using CFD
450(8)
5.7 Design of Venturi scrubber for filtered containment venting system
458(19)
5.8 Closure
477(10)
References
481(4)
Further reading
485(2)
6 Modelling of core melt scenarios in nuclear reactors
487(80)
Arun K. Nayak
Parimal P. Kulkarni
Pradeep Pandey
Sumit V. Prasad
6.1 Introduction to severe accident phenomena and progression in water-cooled reactors
489(4)
6.2 Current status of application of CFD codes for severe accidents
493(6)
6.3 Simulation of in-vessel retention of corium in PHWRs using CFD
499(25)
6.4 CFD simulation of debris bed coolability
524(15)
6.5 Modelling of melt coolability in ex-vessel conditions
539(19)
6.6 Closure
558(9)
References
561(4)
Further reading
565(2)
7 Application of CFD for assessment of containment safety
567(96)
Sunil Ganju
Aditya Karanam
Shubham Mishra
Nandan Saha
Bhuvaneshwar Gera
Priyanshu Goyal
Pavan K. Sharma
Ashish V. Shelke
7.1 Introduction
568(1)
7.2 Role of CFD in addressing containment safety issues
569(2)
7.3 Application of CFD for hydrogen distribution studies in post-accident containment atmospheres of Indian reactors
571(28)
7.4 Modelling of hydrogen recombination using CFD
599(17)
7.5 CFD modelling of hydrogen combustion for containment safety applications
616(25)
7.6 CFD analysis of hydrocarbon fireballs for safety assessment of nuclear power plants
641(12)
7.7 Conclusions and recommendations
653(2)
7.8 Limitations
655(1)
7.9 Further work
656(7)
References
657(6)
8 Modeling of fire with CFD for nuclear power plants (NPPs)
663(66)
Pavan K. Sharma
8.1 Background
663(1)
8.2 Present and evolving scenario (industry specific scenario)
663(1)
8.3 Dynamic safety requirements
664(1)
8.4 Boundary for conventional fire modeling
664(1)
8.5 Fire modeling framework
664(1)
8.6 Design fire for industrial applications
665(1)
8.7 The understanding of flame and plume
666(2)
8.8 LES-based CFD procedure
668(4)
8.9 Plume puffing frequency
672(4)
8.10 Isothermal simulation for puffing
676(2)
8.11 Plume rise time
678(1)
8.12 Oscillatory ceiling opening
679(1)
8.13 Ceiling opening with different aspect ratios
680(3)
8.14 Gravity currents for fire
683(6)
8.15 Ceiling opening with wall opening
689(1)
8.16 Fire and its characteristics
689(16)
8.17 Fire safety concern for Nuclear Power Plant
705(1)
8.18 The role of CFD in fire modeling
706(3)
8.19 Fire Hazard Analysis (FHA) using the strength of CFD for NPPS and allied facilities
709(1)
8.20 Methodology and technical basis
709(1)
8.21 Development of design fire
710(12)
8.22 Closure
722(7)
References
722(7)
9 Applications of computational fluid dynamics in design of sodium-cooled fast reactors
729(26)
Karuppanna Velusamy
9.1 Introduction
729(2)
9.2 Thermal hydraulic characteristics of SFR
731(3)
9.3 Thermal hydraulic design limits
734(1)
9.4 CFD analysis requirements
734(1)
9.5 Typical case studies
735(17)
9.6 Conclusions
752(3)
Acknowledgments
752(1)
References
753(2)
10 CFD and systems thermal-hydraulic analysis in the design and safety assessment of high-temperature reactors
755(46)
Pieter G. Rousseau
Chad G. Du Toit
Herman J. Van Antwerpen
10.1 Introduction
755(6)
10.2 Gas-cooled reactor analysis
761(15)
10.3 Molten salt-cooled reactor analysis
776(13)
10.4 Industrial perspective
789(4)
10.5 Summary and conclusions
793(8)
References
794(7)
11 Heat transfer and computational fluid dynamics for molten salt reactor technologies
801(34)
Piyush Sabharwall
Manuele Aufiero
Massimiliano Fratoni
11.1 Introduction
801(2)
11.2 Molten salts as heat transfer coolant
803(2)
11.3 Figures of merit development for coolant thermal-hydraulic performance
805(8)
11.4 Convective heat transfer correlations in molten salts
813(3)
11.5 CFD applications for MSR technologies
816(8)
11.6 MSR technical challenges
824(2)
11.7 Conclusions
826(9)
Acknowledgments
826(1)
References
826(3)
Further reading
829(6)
12 Conclusions and future recommendation
835(16)
Jyeshtharaj B. Joshi
Arun K. Nayak
12.1 Simulation of single-phase turbulent flows in nuclear reactors
836(3)
12.2 Simulation of multiphase flows
839(4)
12.3 Role of Prandtl number Pr
843(1)
12.4 Relationship between flow pattern and design
844(1)
12.5 Multiscale modelling
844(1)
12.6 Current status of CFD validation through experiments
845(6)
References
846(5)
Index 851
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 Arun Kumar Nayak is the Outstanding Scientist and Head of the Thermal Hydraulics Section of Bhabha Atomic Research Centre and a Professor at Hombi Bhabha National Institute in Mumbai, India. He is a graduate in Mechanical Engineering from NIT, Rourkela, India, and joined the Reactor Design and Development Group in BARC in 1990 after completing the Orientation Course in Nuclear Engineering from the BARC Training School in Mumbai, India. He obtained his PhD in Nuclear Engineering from Tokyo Institute of Technology, Japan, and has worked at the Interfaculty Reactor Institute of the Technical University Delft, as well as in the Nuclear Power Safety Division of the Royal Institute of Technology, in Stockholm as a Post-doc Scientist. He has also worked at Institute of Nuclear Energy (IKE) in the University of Stuttgart under the DST-DAAD programme. He has received several awards and is a Fellow of Maharashtra Academy of Science and Indian National Academy of Engineering. He has published more than 350 papers in academic journals and conferences, and is an Associate Editor of the journals Computational Thermal Sciences” and Frontiers in Energy Research Nuclear Energy” and is a member of the editorial board of Life Cycle Reliability and Safety Engineering."