| Description |
1 online resource |
| Series |
Woodhead Publishing series in energy |
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Woodhead Publishing in energy
|
| Contents |
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 |
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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 |
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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 |
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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 |
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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 |
| Notes |
Print version record |
| Subject |
Nuclear reactors -- Safety measures.
|
|
Nuclear reactor accidents.
|
|
Nuclear reactor accidents
|
|
Nuclear reactors -- Safety measures
|
| Form |
Electronic book
|
| Author |
Kulkarni, Parimal
|
| ISBN |
9780128223055 |
|
0128223057 |
|
