The text comprehensively discusses basis of mathematical modelling of the heat transfer process in a fast reactor cooled by sodium in a single volume. The text will be helpful for senior undergraduate, graduate students and academic researchers in the fields of nuclear engineering, mechanical engineering, and power cycle engineering.

Chapter 1 Introduction1.1 General1.2 Basics of Breeding1.3 Uranium Utilization1.4 Components of Fast Reactors 1.5 Overview of Fast Reactor Programs1.6 Need for Dynamic Simulation1.7 Design Basis 1.8 Plant Protection System1.9 Sensors and Response Time1.10 Scope of Dynamic Studies1.11 Modelling Development References AssignmentChapter 2 Description of Fast Reactors 2.1 Introduction 2.2 Fast Breeder Test Reactor (FBTR) 2.2.1. Reactor Core2.2.2 Reactor Assembly 2.2.3. Sodium Systems2.2.4 Decay Heat Removal2.2.5 Generating Plant2.2.6 Instrumentation and Control2.2.7 Safety2.3 Prototype Fast Breeder Reactor2.3.1 Reactor Core2.3.2 Reactor Assembly2.3.3 Main Heat Transport System2.3.4 Steam Water System2.3.5 Instrumentation and control2.3.6 Safety2.4 Neutronic Characteristics of FNRs2.5 Thermal-Hydraulic Characteristics of FNR References AssignmentChapter 3 Reactor Heat Transfer 3.1 Introduction3.2 Reactor Core 3.2.1 Core Description 3.2.2 Fuel Pin 3.2.3 Subassembly3.3 Coolant Selection 3.4 Control Material Selection3.5 Structural Material Selection3.6 Heat Generation3.7 Reactivity Feedback 3.7.1 Doppler Effect 3.7.2 Sodium Density and Void Effects 3.7.3 Fuel Axial Expansion Effect 3.7.4 Structural Expansion 3.7.5 Bowing3.8 Decay Heat3.9 Solution Methods 3.9.1 Prompt Jump Approximation 3.9.2 Runge Kutta Method 3.9.3 Kaganove Method 3.9.4 Comparison of different Methods 3.9.5 Solution Methodology3.10 Heat Transfer in Primary System 3.10.1 Core Thermal Model 3.10.2 Fuel Restructuring 3.10.3 Gap Conductance 3.10.4 Fuel Thermal Model 3.10.5 Solution Technique3.11 Determination of Peak Temperatures: Hot Spot Analysis3.12 Core Thermal Model validation in FBTR and SUPER PHENIX 3.13 Mixing of Coolant Streams in Upper Plenum 3.13.1 Solution Technique 3.14 Lower Plenum/Cold Pool3.15 Grid Plate 3.16 Heat Transfer Correlations for Fuel Rod Bundle References AssignmentChapter 4 IHX Thermal Model4.1 Introduction4.2 Experience in PHENIX4.3 Thermal Model4.4 Solution Techniques 4.4.1 Nodal Heat Balance Scheme 4.4.2 Finite Differencing Scheme4.5 Choice of Numerical Scheme 4.5.1 Nodal Heat Balance for Unbalanced Flows 4.5.2 Modified Nodal Heat Balance Scheme (MNHB)4.6 Heat Transfer Correlations4.7 ValidationReferencesAssignmentChapter 5 Thermal Model of Piping5.1 Introduction5.2 Thermal Model5.3 Solution Methods5.4 Comparison of Piping ModelsReferencesAssignmentChapter 6 Sodium Pump6.1 Introduction6.2 Electromagnetic Pumps6.3 Centrifugal Pump 6.3.1 Pump Hydraulic Model 6.3.2 Pump Dynamic Model 6.3.3 Pump Thermal ModelReferencesAssignmentChapter 7 Transient Hydraulics Simulation7.1Introduction7.2Momentum Equations 7.3Free Level Equations7.4Core Coolant Flow Distribution 7.5IHX Pressure Drop Correlations 7.5.1 Resistance Coefficient for Cross Flow 7.5.2. Resistance Coefficient for Axial Flow7.6 Pump Characteristics7.7 Computational Model7.8 Validation Studies7.9 Secondary Circuit Hydraulics 7.9.1 Secondary Hydraulics Model 7.9.2 Natural Convection Flow in Sodium-Validation StudiesReferencesAssignmentChapter 8 Steam Generator8.1 Introduction8.2 Heat Transfer Mechanisms8.3 Steam Generator Designs 8.3.1. Conventional Fossil Fuelled Boilers 8.3.1.1 Drum Type 8.3.1.2 Once Through Steam Generators 8.3.2 Sodium Heated Steam Generators8.4 Thermodynamic Models 8.5 Mathematical Model 8.6 Heat Transfer Correlations 8.6.1 Single Phase Liquid Region 8.6.2 Nucleate Boiling 8.6.3 Dry-Out 8.6.4 Post Dry-Out 8.6.5 Superheated Region 8.6.6 Sodium Side Heat Transfer8.7 Pressure Drop8.8 Computational Model 8.8.1Solution of Water /Steam Side Equations 8.8.2 Solution of Sodium, Shell, And Tube Wall Equations 8.9 Steam Generator Model ValidationReferencesAssignmentChapter 9 Computer Code Development9.1 Introduction9.2 Organization of DYNAM9.3 Axisymmetric Code STITH-2D 9.4 Comparison of Predictions of DYANA-P And DYANA-HMReferencesChapter 10 Specifying Sodium Pumps Coast-Down Time10.1 Introduction10.2 Impact of Coast Down Time in Loop Type FNR10.3 Impact of Coast Down Time in Pool Type FNR10.4 Considerations for Deciding Flow Coast Down Time10.5 Scram Threshold Vs Coast Down Time 10.5.1. FHT Effect on Maximum Temperatures 10.5.2 FHT to Avoid Scram for Short Power Failure10.6 Secondary pump FHT10.7 Primary FHT for Unprotected Loss of FlowReferencesAssignmentChapter 11 Plant Protection System11.1 Introduction11.2 Limiting Safety System Settings for FBTR 11.2.1 Safety Signals and Settings 11.2.2 Limiting Safety System Adequacy for FBTR11.3 Limiting Safety System Settings for PFBR 11.3.1 Design Basis Events 11.3.2 Core Design Safety Limits 11.3.3 Selection of Scram Parameters11.4 Shutdown System11.5 Event AnalysisReferencesAssignmentChapter 12 Decay Heat Removal System 12.1 Introduction 12.2 Natural Convection Basics 12.3 DHR System Options in FNR 12.3.1 DHR in Primary Sodium 12.3.2 DHR in Secondary Sodium 12.3.3 Steam Generator Auxiliary Cooling System 12.3.4 DHR Through Steam-Water System 12.3.5 Reactor Vessel Auxiliary Cooling System 12.4 DHR in FBTR 12.4.1 Heat Removal By Air In SG Casing 12.4.2 Loss of Offsite and Onsite Power with SG Air Cooling 12.4.3 Loss Of Offsite And Onsite Power Without Reactor Trip12.5 DHR in PFBR 12.5.1 Thermal Model 12.5.2 Decay Heat Exchanger (DHX) Model 12.5.3 Hot Pool Model 12.5.4 Air Heat Exchanger Model (AHX) Model 12.5.5 Piping 12.5.6 Expansion Tank 12.5.7 Air Stack/Chimney 12.5.8 Hydraulic Model 12.5.9 DHDYN Validation on SADHANA Loop12.6 Role of Inter Wrapper Flow12.7 Role of Secondary thermal capacityReferencesAssignmentChapter 13 Modelling of Large Sodium-Water Reaction13.1 Introduction13.2 Leak Rate 13.2.1 Water Leak Rate model 13.2.2 Steam leak rate model 13.3 Reaction site dynamics 13.3.1 Spherical bubble model 13.3.2 Columnar bubble model 13.3.3 Solution technique 13.3.4 Validation of Reaction site model13.4 Sodium Side System Transient13.5 Discharge Circuit System Transient13.6 Analysis of Pressure Transients for PFBR13.7 Failure of a greater number of tubes than design basis leakReferencesAssignment