LEADER 04887nam 22006373u 450 001 9910148607303321 005 20230120014219.0 010 $a1-4831-4524-7 035 $a(CKB)3710000000030223 035 $a(EBL)1598195 035 $a(SSID)ssj0001064513 035 $a(PQKBManifestationID)12479722 035 $a(PQKBTitleCode)TC0001064513 035 $a(PQKBWorkID)11053379 035 $a(PQKB)10061243 035 $a(MiAaPQ)EBC1598195 035 $a(EXLCZ)993710000000030223 100 $a20140127d1981|||| u|| | 101 0 $aeng 135 $aur|n|---||||| 181 $ctxt 182 $cc 183 $acr 200 10$aThermal Design of Nuclear Reactors 210 $aBurlington $cElsevier Science$d1981 215 $a1 online resource (415 p.) 225 0 $aPergamon international library of science, technology, engineering, and social studies Thermal design of nuclear reactors 300 $aDescription based upon print version of record. 311 $a0-08-024215-4 327 $aCover 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; INTRODUCTION 327 $aTEMPERATURE 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 COOLANTS 327 $aIMPROVEMENT 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 POWER 327 $aPRESSURE 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 temperature 327 $aMINIMUM 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 Reactors 327 $aPublisher Summary 330 $aThermal Design of Nuclear Reactors 606 $aNuclear reactors -- Design and construction 606 $aNuclear reactors$xDesign and construction 606 $aMechanical Engineering$2HILCC 606 $aEngineering & Applied Sciences$2HILCC 606 $aNuclear Engineering$2HILCC 615 4$aNuclear reactors -- Design and construction. 615 0$aNuclear reactors$xDesign and construction. 615 7$aMechanical Engineering 615 7$aEngineering & Applied Sciences 615 7$aNuclear Engineering 676 $a621.48/32 676 $a621.4832 700 $aWinterton$b R. H. S$0727837 801 0$bAU-PeEL 801 1$bAU-PeEL 801 2$bAU-PeEL 906 $aBOOK 912 $a9910148607303321 996 $aThermal Design of Nuclear Reactors$92857378 997 $aUNINA