Severe accidents in nuclear reactors : corium retention technologies and insights /

Detalles Bibliográficos
Clasificación:Libro Electrónico
Autor principal: Nayak, Arun K. (Engineer)
Otros Autores: Kulkarni, Parimal
Formato: Electrónico eBook
Idioma:Inglés
Publicado: Duxford : Woodhead Publishing, 2021.
Colección:Woodhead Publishing in energy.
Temas:
Nuclear reactors > Safety measures.
Nuclear reactor accidents.
R�eacteurs nucl�eaires > S�ecurit�e > Mesures.
R�eacteurs nucl�eaires > Accidents.
Nuclear reactor accidents
Nuclear reactors > Safety measures
Acceso en línea:Texto completo
Tabla de Contenidos:
  • Front cover
  • Half title
  • Title Page
  • Copyright
  • Contents
  • Foreword
  • Nuclear Power
  • Preface
  • Chapter 1 Introduction
  • 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
  • 1.6.1 Scenario prior to TMI: Accidents in military reactors
  • 1.6.2 The accident at TMI
  • 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
  • 1.12.1 Analysis of Fukushima accidents
  • 1.12.2 Consequences of Fukushima accident
  • 1.12.3 Implications in new reactor designs
  • 1.13 Closure
  • References
  • Chapter 2 Progression of severe accidents in water cooled reactors
  • 2.1 Introduction
  • 2.2 Transient evolution of severe accident progression
  • 2.2.1 Light water reactors
  • 2.2.2 Severe accident progression in generic PHWRs
  • 2.2.3 Severe accident progression in old generation Indian PHWRs
  • 2.2.4 Pressure vessel type non CANDU PHWRs (Atucha type)
  • 2.3 Managing core melt accidents
  • 2.3.1 The in-vessel melt retention
  • 2.3.2 The ex-vessel corium coolability (core catcher)
  • 2.4 Managing core melt accidents in PHWRs
  • 2.5 Closure
  • References
  • Chapter 3 Experiments with high temperature melts: challenges and issues
  • 3.1 Introduction
  • 3.2 Scaling consideration for simulant materials
  • 3.3 High temperature melt generation
  • 3.3.1 Electrical melting furnaces
  • 3.3.2 Induction melting
  • 3.4 Thermite melting.
  • 3.4.1 Utilization of thermite for generating corium simulants
  • 3.5 Measurement of high temperatures
  • 3.5.1 Thermocouples
  • 3.5.2 Pyrometers
  • 3.6 Safety issues in conducting high temperature melts
  • 3.6.1 Electrical short circuits and fires
  • 3.6.2 Chemical fires
  • 3.6.3 Explosions
  • 3.7 Summary
  • References
  • Chapter 4 Corium coolability in PHWRs: In-vessel retention
  • 4.1 Introduction
  • 4.2 Basis for scaling
  • 4.2.1 Scaling philosophy for decay heat dominating regime
  • 4.2.2 Scaling philosophy for stored heat dominated regime
  • 4.3 In-calandria corium coolability with decay heat simulation for a prolonged duration
  • 4.3.1 Details of experimental setup
  • 4.3.2 Scaling of the experiment
  • 4.3.3 Experimental findings
  • 4.3.4 Insights from the experiments
  • 4.4 In calandria corium coolability in stored heat dominated regime
  • 4.4.1 In calandria corium coolability with MnO-TiO2 simulant material at 2000�C
  • 4.4.2 In-calandria corium coolability at high temperature (2300�C) with prototypic simulant material
  • 4.4.3 In calandria corium coolability with 100 kg melt at prototypic condition
  • 4.4.4 In calandria corium coolability with 500 kg melt at prototypic condition
  • 4.5 Integrity of calandria vessel weld joints against high temperature load
  • 4.5.1 Introduction
  • 4.5.2 The Experimental setup
  • 4.5.3 Process Instrumentation
  • 4.5.4 Experiments conducted
  • 4.5.5 Results
  • 4.5.6 Summary
  • 4.6 Influence of moderator drain pipe in calandria vessel on retention of molten corium
  • 4.6.1 Introduction
  • 4.6.2 Simulation of retention of molten corium in calandria vessel with moderator drain pipe
  • 4.7 Critical heat flux on curved calandria vessel vs the imposed heat flux due to molten corium
  • 4.7.1 Introduction
  • 4.7.2 Investigation of CHF on curved vessel
  • 4.7.3 Phenomenology of occurrence of CHF.
  • 4.7.4 Variation of heat transfer coefficient
  • 4.7.5 Effect of moderator drain pipe on critical heat flux
  • 4.8 Insights
  • References
  • Chapter 5 Numerical modelling of in-vessel retention in PHWRs
  • 5.1 Introduction
  • 5.2 Heat transfer in calandria vessel
  • 5.2.1 Heat transfer modes in the vessel
  • 5.2.2 Model assumptions
  • 5.2.3 Governing equations
  • 5.2.4 Solution strategy
  • 5.2.5 Model validation
  • 5.2.6 Application of model to prototypic condition
  • 5.2.7 Discussions
  • 5.2.8 Effect of reducing decay heat
  • 5.2.9 Summary
  • 5.3 CFD simulation of melt pool coolability in calandria vessel in prototypic condition
  • 5.3.1 Modelling and solution algorithm
  • 5.3.2 Material properties
  • 5.3.3 Corium coolability behavior inside the calandria
  • 5.3.4 Summary
  • 5.4 Simulation of thermal and structural loads on the calandria vessel
  • 5.4.1 Introduction
  • 5.4.2 Thermal-structural analysis of calandria vessel
  • 5.5 Closure
  • References
  • Chapter 6 Ex-vessel molten corium coolability
  • 6.1 Introduction
  • 6.2 Issues in exvessel corium coolability
  • 6.2.1 Corium coolability issues in top flooding
  • 6.2.2 Corium coolability issues in bottom flooding
  • 6.2.3 Issues in corium coolability with top flooding and indirect vessel cooling
  • 6.3 Corium coolability under top flooding
  • 6.3.1 Experimental investigations
  • 6.3.2 Modeling aspects of corium coolability under top flooding
  • 6.3.3 New model development of melt coolability studies under top flooding
  • 6.3.4 Influence of thermo-physical properties of the melt on coolability
  • 6.3.5 Scaling criteria for simulation of coolabilty of molten corium
  • 6.3.6 Further validation of model on water ingression in top flooding
  • 6.3.7 Validation of model with experimental data
  • 6.3.8 Summary
  • 6.4 Corium coolability with bottom flooding
  • 6.4.1 Experiments performed.
  • 6.4.2 Model development
  • 6.4.3 Scalability of bottom flooding
  • 6.5 Corium coolability in core catcher with external vessel cooling and top flooding
  • 6.5.1 The rationale
  • 6.5.2 Corium coolability at prototypic condition
  • 6.5.3 Demonstration of long term corium coolability and decay heat removal
  • 6.6 Closure
  • References
  • Chapter 7 Molten core concrete interaction and ablation of sacrificial material in ex-vessel scenarios
  • 7.1 Introduction
  • 7.2 Molten core concrete interaction (MCCI)
  • 7.2.1 Phenomenology of MCCI
  • 7.2.2 State of the art on molten core concrete interaction
  • 7.2.3 Numerical modelling of 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
  • 7.7.1 Characteristics of sacrificial material
  • 7.7.2 Phenomenology of ablation of sacrificial material in core catcher
  • 7.7.3 Numerical modelling of the ablation phenomenon
  • 7.7.4 Benchmarking of the model with experimental data
  • 7.8 Application to prototypic condition
  • 7.9 Closure
  • References
  • Chapter 8 Fuel coolant interaction
  • 8.1 Introduction
  • 8.2 Mechanism of steam explosion
  • 8.3 State of the art
  • 8.3.1 Small scale experiments
  • 8.3.2 Medium scale experiments
  • 8.3.3 Insights from these experiments
  • 8.3.4 Prototypic large scale experiments
  • 8.4 Fuel coolant interaction experiments
  • 8.4.1 Low temperature experiments
  • 8.4.2 Details of the experiments conducted
  • 8.4.3 Test section details
  • 8.4.4 Operating procedures
  • 8.4.5 Post test analysis
  • 8.4.6 Summary
  • 8.5 High temperature experiments with prototypic melt
  • 8.5.1 Test matrix
  • 8.5.2 Test section details
  • 8.5.3 Results and discussions
  • 8.5.4 Findings from the experiments
  • 8.6 Discussions.
  • 8.7 Further discussions
  • 8.8 Closure
  • References
  • Chapter 9 Debris bed hydrodynamics, convective heat transfer and dryout
  • 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
  • 9.4.1 Experimental set-up
  • 9.4.2 Evaluation of debris bed friction characteristics
  • 9.4.3 Experiments under boiling two phase conditions
  • 9.4.4 Dryout behavior
  • 9.4.5 Assessment of capability of models for prediction of dryout heat flux and pressure drop behavior
  • 9.5 Natural convection heat transfer behavior of a radially stratified particulate debris bed
  • 9.5.1 Experimental facility
  • 9.5.2 Experiments for dryout behavior of radially stratified bed
  • 9.6 Natural convection heat transfer behavior of a large multidimensional debrs bed with volumetric heat generation
  • 9.6.1 Experimental setup
  • 9.6.2 Operating procedure
  • 9.6.3 Temperature profiles and contours at different locations in the bed
  • 9.6.4 Heat transfer characteristics between bed and overlying water pool
  • 9.7 Closure
  • References
  • Chapter 10 Conclusions
  • 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
  • Index
  • Back cover.

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