
Severe Accidents in Nuclear Reactors
Corium Retention Technologies and Insights
- 1st Edition - August 2, 2021
- Imprint: Woodhead Publishing
- Authors: Arun K. Nayak, Parimal Pramod Kulkarni
- Language: English
- Paperback ISBN:9 7 8 - 0 - 1 2 - 8 2 2 3 0 4 - 8
- eBook ISBN:9 7 8 - 0 - 1 2 - 8 2 2 3 0 5 - 5
Severe Accidents in Nuclear Reactors: Corium Retention Technologies and Insights presents an authoritative and practical analysis of the latest severe accident management strategie… Read more

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Request a sales quoteSevere 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.
- Provides a step-by-step guide to various severe accident management experiments
- Includes evidence on the termination of severe accident progressions
- Validates several severe accident codes
Nuclear reactor designers, regulators, operators, academic professionals, researchers, PhD Scholars and students working in the field of severe accidents and nuclear safety. Utilities and industries operating nuclear power plants for formulating the severe accident management strategies
- Cover Image
- Title Page
- Copyright
- Table of Contents
- Foreword
- Nuclear Power – an Integral Part of the Energy Solution for the Current Century
- Preface
- 1 Introduction
- Chapter Outline
- Abstract
- 1.1 History of light water reactor safety
- 1.2 Pre-history of nuclear safety and nuclear safety assessment
- 1.3 Evolution of siting criteria
- 1.4 Safety in design of nuclear reactors
- 1.5 Risk of nuclear power
- 1.6 The nuclear accidents and lessons learnt
- 1.7 Evolution of safety in design of new reactors in post-TMI accident scenario
- 1.8 The accident at Chernobyl, 1986
- 1.9 Initiation of severe accident research
- 1.10 Concept of core catcher: How cooling is achieved in the Core Catcher?
- 1.11 Evolution of small modular reactors
- 1.12 Another blow to nuclear industry – the Fukushima accident
- 1.13 Closure
- References
- 2 Progression of severe accidents in water cooled reactors
- Chapter Outline
- Abstract
- 2.1 Introduction
- 2.2 Transient evolution of severe accident progression
- 2.3 Managing core melt accidents
- 2.4 Managing core melt accidents in PHWRs
- 2.5 Closure
- References
- 3 Experiments with high temperature melts: challenges and issues
- Chapter Outline
- Abstract
- 3.1 Introduction
- 3.2 Scaling consideration for simulant materials
- 3.3 High temperature melt generation
- 3.4 Thermite melting
- 3.5 Measurement of high temperatures
- 3.6 Safety issues in conducting high temperature melts
- 3.7 Summary
- References
- 4 Corium coolability in PHWRs: In-vessel retention
- Chapter Outline
- Abstract
- 4.1 Introduction
- 4.2 Basis for scaling
- 4.3 In-calandria corium coolability with decay heat simulation for a prolonged duration
- 4.4 In calandria corium coolability in stored heat dominated regime
- 4.5 Integrity of calandria vessel weld joints against high temperature load
- 4.6 Influence of moderator drain pipe in calandria vessel on retention of molten corium
- 4.7 Critical heat flux on curved calandria vessel vs the imposed heat flux due to molten corium
- 4.8 Insights
- References
- 5 Numerical modelling of in-vessel retention in PHWRs
- Chapter Outline
- Abstract
- 5.1 Introduction
- 5.2 Heat transfer in calandria vessel
- 5.3 CFD simulation of melt pool coolability in calandria vessel in prototypic condition
- 5.4 Simulation of thermal and structural loads on the calandria vessel
- 5.5 Closure
- References
- 6 Ex-vessel molten corium coolability
- Chapter Outline
- Abstract
- 6.1 Introduction
- 6.2 Issues in exvessel corium coolability
- 6.3 Corium coolability under top flooding
- 6.4 Corium coolability with bottom flooding
- 6.5 Corium coolability in core catcher with external vessel cooling and top flooding
- 6.6 Closure
- References
- 7 Molten core concrete interaction and ablation of sacrificial material in ex-vessel scenarios
- Chapter Outline
- Abstract
- 7.1 Introduction
- 7.2 Molten core concrete interaction (MCCI)
- 7.3 Benchmarking of the model
- 7.4 Thermal decomposition characteristics of different concretes
- 7.5 Corium coolability during MCCI under top flooded conditions
- 7.6 Summary
- 7.7 Ablation behaviour of sacrificial material
- 7.8 Application to prototypic condition
- 7.9 Closure
- References
- 8 Fuel coolant interaction
- Chapter Outline
- Abstract
- 8.1 Introduction
- 8.2 Mechanism of steam explosion
- 8.3 State of the art
- 8.4 Fuel coolant interaction experiments
- 8.5 High temperature experiments with prototypic melt
- 8.6 Discussions
- 8.7 Further discussions
- 8.8 Closure
- References
- 9 Debris bed hydrodynamics, convective heat transfer and dryout
- Chapter Outline
- Abstract
- 9.1 Introduction
- 9.2 Formation and characterization of debris beds formed during severe accident
- 9.3 Issues in coolability of heat generating debris beds
- 9.4 Hydrodynamics and heat transfer behavior of irregularly shaped particulate debris bed
- 9.5 Natural convection heat transfer behavior of a radially stratified particulate debris bed
- 9.6 Natural convection heat transfer behavior of a large multidimensional debrs bed with volumetric heat generation
- 9.7 Closure
- References
- 10 Conclusions
- Chapter Outline
- Abstract
- 10.1 Introduction
- 10.2 Summary of severe accident phenomena in nuclear power plants
- 10.3 Severe accident management strategies
- 10.4 SAMG for new nuclear plants
- 10.5 Insights from corium cooling studies
- 10.6 Way forward
- References
- Edition: 1
- Published: August 2, 2021
- No. of pages (Paperback): 394
- No. of pages (eBook): 394
- Imprint: Woodhead Publishing
- Language: English
- Paperback ISBN: 9780128223048
- eBook ISBN: 9780128223055
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Arun K. Nayak
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