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.
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Table of Contents
1. Introduction
Arun K. Nayak
2. Computational fluid dynamics
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
3. CFD model development for two-phase flows
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
4. Evaluation of safety of light-water-cooled reactors using CFD
Thomas H�hne
5. Design of passive safety systems for advanced reactors using CFD
Jyeshtharaj B. Joshi, Arun K. Nayak, Nitin Minocha, Eshita Pal, Ankur Kumar, Mukesh Kumar, Avinash Moharana
6. Modelling of core melt scenarios in nuclear reactors
Arun K. Nayak, Parimal P. Kulkarni, Pradeep Pandey, Sumit V. Prasad
7. Application of CFD for assessment of containment safety
Sunil Ganju, Aditya Karanam, Shubham Mishra, Nandan Saha, Bhuvaneshwar Gera, Priyanshu Goyal, Pavan K. Sharma, Ashish V. Shelke
8. Modeling of fire with CFD for nuclear power plants (NPPs)
Pavan K. Sharma
9. Applications of computational fluid dynamics in design of sodium-cooled fast reactors
Karuppanna Velusamy
10. CFD and systems thermal-hydraulic analysis in the design and safety assessment of high-temperature reactors
Pieter G. Rousseau, Charl G. Du Toit, Herman J. Van Antwerpen
11. Heat transfer and computational fluid dynamics for molten salt reactor technologies
Piyush Sabharwall, Manuele Aufiero, Massimiliano Fratoni
12. Conclusions and future recommendation
Jyeshtharaj B. Joshi, Arun K. Nayak
Authors
Jyeshtharaj Joshi Emeritus Professor, Department of Atomic Energy, Mumbai, India. 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 K. Nayak Outstanding Scientist and Head, Thermal Hydraulics Section of Bhabha Atomic Research CentreProfessor, Hombi Bhabha National Institute, Mumbai, India. 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."
