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 corium coolability, providing the reader with an in-depth understanding by presenting the insights obtained from simulated severe accidents.
In addition, the book validates several severe accident codes and provides evidence on the termination of severe accident progressions to help the reader evaluate the safety of existing reactors and design the next generation of nuclear reactors.
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Table of Contents
1. Introduction 2. Progression of severe accidents in Water Cooled Reactors 3. Experiments with high temperature corium stimulants 4. Corium coolability in PHWRs: In-vessel retention 5. Numerical Modelling of In-vessel Retention in PHWRs 6. Corium coolability in ex-vessel core catcher 7. Numerical modelling of ablation of sacrificial material in ex-vessel core catcher 8. Fuel coolant interaction 9. Debris bed coolability 10. Conclusions
Authors
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." Parimal Pramod Kulkarni Institute of Chemical Technology, Mumbai, India. Parimal Pramod Kulkarni, a Chemical Engineering Graduate from Institute of Chemical Technology, Mumbai, India, joined Reactor Design and Development Group in BARC in 2005 after completing his masters in Chemical Engineering from Indian Institute of Technology, Kanpur. He obtained his PhD in Engineering Sciences from Homi Bhabha National Institute, Mumbai, India, in year 2015. He has also worked at Institute of Nuclear Energy (IKE), University of Stuttgart during 2008-09 in the field of debris bed coolability. He has received the DAE Young Engineer Award, 2012 and group achievement award in 2015. He has published more than 50 papers in academic Journals and Conferences. Currently he is working as Scientific Officer in Thermal Hydraulics Section, Reactor Engineering Division, BARC. He has done extensive research in the field of severe accident management which has contributed towards safety enhancement of Indian Advanced Heavy Water and Pressurized Heavy Water Reactors.
