Thermal Design of Nuclear Reactors [[electronic resource]]
(Visualizza in formato marc)
(Visualizza in BIBFRAME)
| Autore: |
Winterton R. H. S
|
| Titolo: |
Thermal Design of Nuclear Reactors [[electronic resource]]
|
| Pubblicazione: | Burlington, : Elsevier Science, 1981 |
| Descrizione fisica: | 1 online resource (415 p.) |
| Disciplina: | 621.48/32 |
| 621.4832 | |
| Soggetto topico: | Nuclear reactors -- Design and construction |
| Nuclear reactors - Design and construction | |
| Mechanical Engineering | |
| Engineering & Applied Sciences | |
| Nuclear Engineering | |
| Note generali: | Description based upon print version of record. |
| Nota di contenuto: | 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; INTRODUCTION |
| TEMPERATURE 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 | |
| IMPROVEMENT 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 | |
| PRESSURE 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 | |
| MINIMUM 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 | |
| Publisher Summary | |
| Sommario/riassunto: | Thermal Design of Nuclear Reactors |
| Titolo autorizzato: | Thermal Design of Nuclear Reactors |
| ISBN: | 1-4831-4524-7 |
| Formato: | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione: | Inglese |
| Record Nr.: | 9910148607303321 |
| Lo trovi qui: | Univ. Federico II |
| Opac: | Controlla la disponibilità qui |