Nuclear systems. Elements of thermal hydraulic design / Volume 2, (2020)

• Record Type: Book
• Other Titles: Elements of thermal hydraulic design
• Further Information: Note: By Neil E. Todreas, Mujid Kazimi.
• Authors: Todreas, Neil E; Kazimi, Mujid S
• Contents: 1. Formulation of the Reactor Thermal Hydraulic Design Problem 1.1 INTRODUCTION 1.2 POWER REACTOR HYDRAULIC CONFIGURATIONS 1.3 BOUNDARY CONDITIONS FOR THE HYDRAULIC PROBLEM 1.4 PROBLEMS TREATED IN THIS BOOK 1.5 FLOW IN SINGLE CHANNELS 1.5.1 UNHEATED CHANNEL 1.5.2 HEATED CHANNEL 1.6 FLOW IN MULTIPLE, HEATED CHANNELS CONNECTED ONLY AT PLENA 1.7 FLOW IN INTERCONNECTED, MULTIPLE HEATED CHANNELS 1.8 APPROACHES FOR REACTOR ANALYSIS 1.8.1 BWR AND LMR CORE ANALYSIS 1.8.2 PWR CORE ANALYSIS 1.9 LUMPED AND DISTRIBUTED PARAMETER SOLUTION APPROACHES PROBLEMS ACRONYMS 2. Scaling of Two-Phase Flows in Complex Nuclear Reactor Systems 2.1 INTRODUCTION 2.1.1 MOTIVATION FOR SCALING ACTIVITY 2.1.2 LIMITATIONS TO THE APPLICATION OF SCALING 2.2 SCOPE OF THIS CHAPTER 2.3 DIMENSIONAL ANALYSIS AND THE BUCKINGHAM PI THEOREM 2.3.1 MOTIVATION FOR USE OF THIS ANALYSIS AND THEOREM 2.3.2 BUCKINGHAM PI THEOREM METHODOLOGY 2.3.3 LIMITATIONS 2.4 LINEAR SCALING 2.4.1 DEFINITION 2.4.2 DEVELOPMENT 2.4.3 LIMITATIONS 2.5 VOLUME (POWER TO VOLUME) SCALING 2.5.1 DEFINITION 2.5.2 DEVELOPMENT 2.5.3 TEST FACILITIES 2.6 ZUBER SCALING CONTRIBUTIONS 2.6.1 ZUBER’S PERSPECTIVE 2.6.2 HIERARCHICAL TWO-TIERED SCALING (H2TS) 2.7 ISHII SCALING 2.7.1 BACKGROUND 2.7.2 THREE-LEVEL SCALING 2.7.3 ADVANTAGES OF THREE-LEVEL SCALING 2.7.4 TEST FACILITIES 2.7.5. ILLUSTRATIVE EXAMPLES 2.8 MODIFIED LINEAR SCALING 2.8.1 GOALS 2.8.2 COMPARISON TO OTHER SCALING APPROACHES 2.8.3 LIMITATIONS 2.9 FRACTIONAL SCALING ANALYSIS (FSA) 2.9.1 THE FSA APPROACH 2.9.2 QUANTITATIVE PHENOMENA RANKING 2.10 DYNAMICAL SYSTEM SCALING 2.10.1 DYNAMICAL SYSTEM SCALING METHODOLOGY FUNDAMENTALS 2.10.2 THE PROCESS METRIC 2.10.3 SIMILARITY CRITERIA PROBLEMS ACRONYMS DEFINITIONS REFERENCES 3 Single, Heated Channel Transient Analysis 3.1 SIMPLIFICATION OF TRANSIENT ANALYSIS 3.2 SOLUTION OF TRANSIENTS WITH APPROXIMATIONS TO THE MOMENTUM EQUATION 3.2.1 SECTIONALIZED, COMPRESSIBLE FLUID (SC) MODEL 3.2.2 MOMENTUM INTEGRAL MODEL (MI) - INCOMPRESSIBLE BUT THERMALLY EXPANDABLE FLUID 3.2.3 SINGLE MASS VELOCITY (SV) MODEL 3.2.4 THE CHANNEL INTEGRAL (CI) MODEL 3.3 SOLUTION OF TRANSIENTS BY THE METHOD OF CHARACTERISTICS (MOC) 3.3.1 BASICS OF THE METHOD 3.3.2 APPLICATIONS TO SINGLE-PHASE TRANSIENTS 3.3.3 APPLICATIONS TO TWO-PHASE TRANSIENTS PROBLEMS ACRONYMS REFERENCES 4 Multiple Heated Channels Connected Only at Plena 4.1 INTRODUCTION 4.2 GOVERNING ONE-DIMENSIONAL, STEADY STATE FLOW EQUATIONS 4.2.1 CONTINUITY EQUATION 4.2.2 MOMENTUM EQUATION 4.2.3 ENERGY EQUATION 4.3 STATE EQUATION 4.4 APPLICABLE BOUNDARY CONDITIONS 4.4.1 CHANNEL BOUNDARY CONDITIONS 4.4.2 PLENA HEAT TRANSFER BOUNDARY CONDITIONS 4.5 THE GENERAL SOLUTION PROCEDURE 4.6 CHANNEL HYDRAULIC CHARACTERISTICS 4.6.1 THE FRICTION-DOMINATED REGIME 4.6.2 THE GRAVITY-DOMINATED REGIME 4.7 COUPLED CONSERVATION EQUATION: SINGLE-PHASE, NONDIMENSIONAL SOLUTION PROCEDURE 4.7.1 DERIVATION OF A SINGLE, COUPLED MOMENTUM–ENERGY EQUATION 4.7.2 NONDIMENSIONAL EQUATIONS 4.7.3 ONSET OF MIXED CONVECTION (UPFLOW) 4.7.4 ADIABATIC CHANNEL FLOW REVERSAL 4.7.5 STABILITY OF COOLED UPFLOW 4.7.6 STABILITY OF HEATED DOWNFLOW 4.7.7 PREFERENCE FOR UPFLOW 4.7.8 LIMITS OF THE SOLUTION PROCEDURE OF SECTION 4.7 4.8 DECOUPLED CONSERVATION EQUATION: ANALYTICAL SOLUTION PROCEDURE FOR HIGH FLOW RATE CASES 4.8.1 PRESCRIBED CHANNEL PRESSURE DROP CONDITION: SOLUTION PROCEDURE 4.8.2 PRESCRIBED TOTAL FLOW CONDITION: SOLUTION PROCEDURE PROBLEMS REFERENCES 5 Analysis of Interacting Channels by the Porous Media Approach 5.1 INTRODUCTION 5.2 APPROACHES TO OBTAINING THE RELEVANT EQUATIONS 5.3 FUNDAMENTAL RELATIONS 5.3.1 POROSITY DEFINITIONS 5.3.2 THEOREMS 5.4 DERIVATION OF THE VOLUME-AVERAGED MASS CONSERVATION EQUATION 5.4.1 SOME USEFUL DEFINITIONS OF AVERAGES 5.4.2 DERIVATION OF THE MASS CONSERVATION EQUATION: METHOD OF INTEGRATION OVER A CONTROL VOLUME 5.4.3 DERIVATION OF THE MASS CONSERVATION EQUATION: APPLICATION OF CONSERVATION PRINCIPLES TO A VOLUME CONTAINING DISTRIBUTED SOLIDS 5.5 DERIVATION OF THE VOLUMETRIC AVERAGED LINEAR MOMENTUM EQUATION 5.6 DERIVATION OF THE VOLUMETRIC AVERAGED EQUATIONS OF ENERGY CONSERVATION 5.6.1 ENERGY EQUATION IN TERMS OF INTERNAL ENERGY 5.6.2 ENERGY EQUATION IN TERMS OF ENTHALPY 5.7 CONSTITUTIVE RELATIONS 5.8 CONCLUSION PROBLEMS REFERENCES 6 Interacting Channels - Subchannel Analysis 6.1 INTRODUCTION 6.2 CONTROL VOLUME SELECTION 6.3 DEFINITIONS OF TERMS IN THE SUBCHANNEL APPROACH 6.3.1 GEOMETRY 6.3.2 MASS FLOW RATES 6.3.3 AXIAL MASS FLOW RATE 6.3.4 TRANSVERSE MASS FLOW RATE PER UNIT LENGTH 6.3.5 MOMENTUM AND ENERGY TRANSFER RATES 6.4 DERIVATION OF THE SUBCHANNEL CONSERVATION EQUATIONS: METHOD OF SPECIALIZATION OF THE POROUS MEDIA EQUATIONS 6.4.1 GEOMETRIC RELATIONS 6.4.2 CONTINUITY EQUATION 6.4.3 ENERGY EQUATION 6.4.4 AXIAL LINEAR MOMENTUM EQUATION 6.4.5 TRANSVERSE LINEAR MOMENTUM EQUATION 6.5 APPROXIMATIONS INHERENT IN THE SUBCHANNEL APPROACH 6.6 COMMONLY USED FORMS OF THE SUBCHANNEL CONSERVATION EQUATIONS 6.6.1 DEFINITIONS 6.6.2 THE COBRA CONTINUITY EQUATION 6.6.3 THE COBRA ENERGY EQUATION 6.6.4 THE COBRA AXIAL MOMENTUM EQUATION 6.6.5 THE COBRA TRANSVERSE MOMENTUM EQUATION 6.7 CONSTITUTIVE EQUATIONS 6.7.1 SURFACE HEAT TRANSFER COEFFICIENTS (PARAMETER 1) AND AXIAL FRICTION AND DRAG (PARAMETER 4) 6.7.2 ENTHALPY (PARAMETER 3) AND AXIAL VELOCITY (PARAMETER 6) TRANSPORTED BY PRESSURE-DRIVEN CROSS-FLOW 6.7.3 TRANSVERSE FRICTION AND FORM DRAG COEFFICIENT (PARAMETER 7) 6.7.4 TRANSVERSE CONTROL VOLUME ASPECT RATIO (PARAMETER 8) 6.7.5 EFFECTIVE CROSS-FLOW RATE FOR MOLECULAR AND TURBULENT MOMENTUM AND ENERGY TRANSPORT (PARAMETERS 2 AND 5) 6.8 BEYOND THE FUNDAMENTALS OF SUBCHANNEL ANALYSIS METHODOLOGY OF SECTIONS 6.1 TO 6.7 6.9 APPLICATION OF THE SUBCHANNEL APPROACH TO CORE ANALYSIS 6.9.1 THE MULTISTAGE AND ONE-STAGE METHODS FOR CORE THERMAL HYDRAULIC SUBCHANNEL ANALYSIS 6.9.2 MULTIPHYSICS SIMULATION OF CORE PERFORMANCE PROBLEMS ACRONYMS REFERENCES 7 Flow Loops 7.1 INTRODUCTION 7.2 LOOP FLOW EQUATIONS 7.3 STEADY STATE, SINGLE-PHASE, NATURAL CIRCULATION 7.3.1 DEPENDENCE ON ELEVATIONS OF THERMAL CENTERS 7.3.2 FRICTION FACTORS IN NATURAL CONVECTION 7.4 STEADY STATE, TWO-PHASE, NATURAL CIRCULATION 7.5 LOOP TRANSIENTS 7.5.1 SINGLE-PHASE LOOP TRANSIENTS 7.5.2 TWO-PHASE LOOP TRANSIENTS 7.5.3 DETAILED PUMP REPRESENTATION PROBLEMS ACRONYMS REFERENCES 8 Steady State and Transient Analysis of Centrifugal Pumps 8.1 INTRODUCTION 8.2 CENTRIFUGAL PUMP PERFORMANCE 8.2.1 STEADY STATE OPERATION OF CENTRIFUGAL PUMPS 8.2.2 PUMP CHARACTERISTIC CURVE VERSUS SYSTEM CURVE 8.2.3 PUMP EFFICIENCY, BRAKE AND HYDRAULIC HORSEPOWER 8.2.4 PREVENTION OF PUMP CAVITATION – NPSH 8.2.5 REQUIRED VERSUS AVAILABLE NPSH 8.2.6 NPSH OF ECCS PUMPS FOLLOWING LOCA 8.2.7 PUMP SIMILARITY RULES 8.3 TRANSIENT ANALYSIS OF REACTOR COOLANT PUMPS 8.3.1 IMPELLER SPEED FOLLOWING LOSS OF POWER TO OPERATING PUMP 8.3.2 LOOP FLOW TRANSIENT 8.3.3 SIMPLIFICATIONS OF LOOP MOMENTUM EQUATION 8.3.4 NON DIMENSIONALIZATION OF IMPELLER ANGULAR MOMENTUM EQUATION 8.3.5 SOLUTION OF FLOW DECAY FOLLOWING PUMP TRIP 8.3.6 FLOW RATE FOLLOWING PUMP STARTUP 8.3.7 PUMP MATHEMATICAL MODEL FOR PLANT EVENTS 9 Transient Analysis of PWR Pressurizer 9.1 INTRODUCTION 9.2 PRESSURIZER DESCRIPTIONS 9.2.1 PRESSURIZER SURGE LINE 9.3 PRESSURIZER FUNCTIONS 9.3.1 PRESSURIZER HEATERS 9.3.2 PRESSURIZER SAFETY AND RELIEF VALVES 9.3.3 PRESSURIZER SPRAY 9.3.4 CHEMICAL AND VOLUME CONTROL SYSTEM 9.3.5 PRESSURIZER CONTROL SYSTEM 9.3.6 PRESSURIZER RESPONSE TO TRANSIENTS 9.4 FORMULATION FOR TRANSIENT ANALYSIS 9.4.1 MODELING APPROACH 9.4.2 PROCESSES CROSSING CONTROL SURFACE 9.4.3 APPLICATION OF CONSERVATION EQUATIONS – CONTINUITY 9.4.4 APPLICATION OF CONSERVATION EQUATIONS – ENERGY 9.4.5 CLOSURE BY CONSTITUTIVE EQUATION – VOLUME CONSTRAINT 9.4.6 SOLUTION OF THE SET OF EQUATIONS 9.4.7 INTEGRATION OF THE STATE VARIABLES 9.5 EVALUATION OF CONSTITUTIVE EQUATIONS 9.5.1 WALL HEAT TRANSFER 9.5.2 CONDENSATION IN PRESSURIZER 9.5.3 MAIN SPRAY FLOW RATE 9.5.4 FLOW THROUGH SAFETY AND RELIEF VALVES 9.5.5 SURGE FLOW RATE 9.5.6 PRESSURIZER HEATER 9.5.7 PRESSURIZER WATER LEVEL 9.5.8 EXCHANGES AT THE BULK INTERFACE 9.6 CLASSIFICATION OF RCS BREAK SIZES 9.6.1 TOTAL LOSS OF FEEDWATER AND ONCE-THROUGH CORE COOLING 9.6.2 THE THREE MILE ISLAND ACCIDENT PROBLEMS ACRONYMS & ABBREVIATIONS REFERENCES 10 Transient Thermal Hydraulic Analysis of Containment 10.1 INTRODUCTION 10.2 TYPES OF CONTAINMENT BUILDINGS 10.3 DESIGN BASIS ACCIDENT (DBA) 10.3.1 LOCA EVALUATION 10.3.2 MSLB EVALUATION 10.4 CONTAINMENT DESIGN LIMITS 10.4.1 CONTAINMENT PRESSURE 10.4.2 CONTAINMENT TEMPERATURE 10.5 MIXTURE OF NON-REACTIVE IDEAL GASES 10.6 CONTAINMENT RESPONSE TO THERMAL LOADS 10.6.1 FORCING FUNCTIONS –FLOW RATES OF MASS AND ENERGY 10.6.2 CONSERVATIONS OF MASS AND ENERGY FOR CONTAINMENT 10.6.3 ALTERNATIVE SOLUTION OF CONTAINMENT EQUATIONS 10.7 PARTITION OF BREAK FLOW 10.8 PHASE CHANGE, POOL – ATMOSPHERE INTERACTION 10.8.1 PROCESSES AT THE VAPOR – LIQUID INTERFACE 10.9 HEAT CONDUCTORS HEAT TRANSFER 10.9.1 CONDENSATION HEAT TRANSFER COEFFICIENT – HEAT CONDUCTORS 10.10 SIMPLE RELATION BETWEEN LOCA ENERGY, PPEAK AND VC 10.11 EQUIPMENT QUALIFICATION 10.12 EFFECT OF DEBRIS ON LONG TERM COOLING 10.12.1 DEBRIS DEFINITION 10.12.2 ECCS FUNCTION 10.12.3 DEBRIS EFFECTS 10.12.4 DEBRIS EFFECTS AT SUMP STRAINER 10.13 CONTAINMENT ANALYSIS COMPUTER CODES PROBLEMS ACRONYMS REFERENCES 11 Analysis of Steam Generators and Condensers 11.1 INTRODUCTION 11.1.1 TYPES OF PWR STEAM GENERATORS 11.1.2 FLOW PATH IN VERTICAL UTSG AND OTSG 11.1.3 DEGREE OF SUBCOOLING AND DEGREE OF SUPERHEAT 11.2 STEAM GENERATOR CONTROL SYSTEM 11.3 STEAM GENERATOR TUBE INTEGRITY 11.3.1 TUBE FAILURE MECHANISMS 11.3.2 VERTICAL VERSUS HORIZONTAL SG 11.3.3 STEAM GENERATOR TUBE RUPTURE EVENT 11.4 ANALYSIS OF PWR OTSG 11.4.1 ONSET OF NUCLEATE BOILING AND SATURATION 11.4.2 HEAT EXCHANGER ANALYSIS – SG ECONOMIZER REGION 11.4.3 TEMPERATURE PROFILE – SG EVAPORATOR REGION 11.5 THERMAL DESIGN OF PWR UTSG 11.6 PWR UTSG DESIGN OPTIMIZATION 11.6.1 UTSG COST COMPO
• Edition: 2nd edition
• Publisher Details: Boca Raton : CRC Press
• Publication Date: 2020
• Extent: 1 online resource, illustrations (black and white)
• Subjects: 621.483; Nuclear reactors -- Fluid dynamics; Heat -- Transmission
• Languages: English
• ISBNs: 9781482239614
• Related ISBNs: 9781482239591; 9781482239607
• Notes: Note: Description based on CIP data; resource not viewed.
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