04886nam 22006373u 450 991014860730332120230120014219.01-4831-4524-7(CKB)3710000000030223(EBL)1598195(SSID)ssj0001064513(PQKBManifestationID)12479722(PQKBTitleCode)TC0001064513(PQKBWorkID)11053379(PQKB)10061243(MiAaPQ)EBC1598195(EXLCZ)99371000000003022320140127d1981|||| u|| |engur|n|---|||||txtccrThermal Design of Nuclear ReactorsBurlington Elsevier Science19811 online resource (415 p.)Pergamon international library of science, technology, engineering, and social studies Thermal design of nuclear reactors Description based upon print version of record.0-08-024215-4 Cover image; Title page; Table of Contents; Other Titles of Interest; Copyright; Preface; Chapter 1: Summary of Reactor Physics; Publisher Summary; INTRODUCTION; FISSION; NEUTRON FLUX AND REACTION CROSS-SECTIONS; CRITICALITY; MODERATORS; BREEDING; THE MULTIPLICATION CONSTANT; NEUTRON FLUX DISTRIBUTION; PRACTICAL REACTOR SYSTEMS; SUMMARY; Chapter 2: Reactor Systems; Publisher Summary; INTRODUCTION; THE PRESSURIZED WATER REACTOR; THE BOILING WATER REACTOR; THE GAS-COOLED REACTOR-THE AGR; THE SODIUM-COOLED FAST BREEDER REACTOR; Chapter 3: Fuel-Rod Design; Publisher Summary; INTRODUCTIONTEMPERATURE DISTRIBUTION IN A CYLINDRICAL FUEL PELLETAllowance for variations in conductivity and heat generation; Effect of porosity on UO2 thermal conductivity; Measurements of UO2 thermal conductivity; HEAT TRANSFER IN THE GAP BETWEEN FUEL AND CLADDING; HEAT TRANSFER THROUGH CYLINDRICAL CLADDING; FISSION GAS RELEASE; DETAILS OF FUEL ROD CONSTRUCTION; Problems; Chapter 4: Forced-Convection Heat Transfer; Publisher Summary; INTRODUCTION; HEAT-TRANSFER COEFFICIENT AND DIMENSIONAL ANALYSIS; HEAT-TRANSFER CORRELATIONS FOR NON-METALS; LIQUID-METAL HEAT TRANSFER; COMPARISON OF COOLANTSIMPROVEMENT OF HEAT TRANSFER USING FINSIMPROVEMENT OF HEAT TRANSFER BY ROUGHENING THE SURFACE; Problems; Chapter 5: Boiling Heat Transfer; Publisher Summary; INTRODUCTION; NUCLEATION; TYPES OF BOILING; FLOW REGIMES IN FORCED-CONVECTION BOILING; Quality, void fraction and slip ratio; HEAT-TRANSFER CORRELATIONS FOR FLOW BOILING; Film boiling; CRITICAL HEAT-FLUX CORRELATIONS FOR FORCED-CONVECTION BOILING OF WATER; Correlations for bulk boiling; Problems; Chapter 6: Fluid Flow; Publisher Summary; INTRODUCTION; PRESSURE DROP WITH A LIQUID COOLANT; PUMPING POWERPRESSURE DROP WITH A GASEOUS COOLANTPRESSURE DROP WITH A TWO-PHASE MIXTURE; CRITICAL FLOW THROUGH BURST PIPES; Problems; Chapter 7: Safety Analysis; Publisher Summary; INTRODUCTION; TIMESCALES OF THE TRANSIENT FLOW AND HEAT-TRANSFER PROCESSES; THE SOURCES OF HEAT; SIMPLE MODEL FOR CLAD TEMPERATURE DURING TRANSIENT; DISCUSSION OF LOSS OF COOLANT ACCIDENTS; THE PROBABILITY APPROACH TO REACTOR SAFETY; THE SODIUM-COOLED FAST REACTOR; Problems; Chapter 8: Core Thermohydraulic Design; Publisher Summary; INTRODUCTION; MAXIMUM CAN TEMPERATURE IN A COOLANT CHANNEL; The maximum fuel temperatureMINIMUM CRITICAL HEAT-FLUX RATIOHOT-CHANNEL FACTORS; GAGS; SUBCHANNEL ANALYSIS; INCREASING HEAT OUTPUT IN GAS-COOLED REACTORS; MAXIMISING STEAM PRODUCTION SUBJECT TO FIXED CRITICAL HEAT FLUX RATIO; Problems; Chapter 9: Steam Cycles; Publisher Summary; INTRODUCTION; THE TEMPERATURE-ENTHALPY DIAGRAM; THE BASIC RANKINE CYCLE; FEED WATER HEATING (REGENERATION); PRACTICAL CYCLES FOR WATER REACTORS; PUMPING POWER AND OTHER LOSSES; RADIOACTIVE STEAM IN THE BWR; CYCLES FOR HIGH-TEMPERATURE REACTORS; NET PLANT EFFICIENCY; COMBINED HEAT AND POWER GENERATION; Problems; Chapter 10: Fusion ReactorsPublisher SummaryThermal Design of Nuclear ReactorsNuclear reactors -- Design and constructionNuclear reactorsDesign and constructionMechanical EngineeringHILCCEngineering & Applied SciencesHILCCNuclear EngineeringHILCCNuclear reactors -- Design and construction.Nuclear reactorsDesign and constructionMechanical EngineeringEngineering & Applied SciencesNuclear Engineering621.48/32621.4832Winterton R. H. S727837AU-PeELAU-PeELAU-PeELBOOK9910148607303321Thermal Design of Nuclear Reactors2857378UNINA