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Small specimen test techniques applied to nuclear reactor vessel thermal annealing and plant life extension
| Small specimen test techniques applied to nuclear reactor vessel thermal annealing and plant life extension |
| Pubbl/distr/stampa | [Place of publication not identified], : ASTM, 1993 |
| Disciplina | 621.48/3 |
| Collana | STP Small specimen test techniques applied to nuclear reactor vessel thermal annealing and plant life extension |
| Soggetto topico |
Nuclear pressure vessels - Testing - Congresses
Annealing of metals - Congresses Nuclear power plants - Maintainability - Congresses Mechanical Engineering Engineering & Applied Sciences Nuclear Engineering |
| ISBN | 0-8031-5250-7 |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910164319403321 |
| [Place of publication not identified], : ASTM, 1993 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Thermal Design of Nuclear Reactors [[electronic resource]]
| Thermal Design of Nuclear Reactors [[electronic resource]] |
| Autore | Winterton R. H. S |
| Pubbl/distr/stampa | Burlington, : Elsevier Science, 1981 |
| Descrizione fisica | 1 online resource (415 p.) |
| Disciplina |
621.48/32
621.4832 |
| Collana | Pergamon international library of science, technology, engineering, and social studies Thermal design of nuclear reactors |
| Soggetto topico |
Nuclear reactors -- Design and construction
Nuclear reactors - Design and construction Mechanical Engineering Engineering & Applied Sciences Nuclear Engineering |
| ISBN | 1-4831-4524-7 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| 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 |
| Record Nr. | UNINA-9910148607303321 |
Winterton R. H. S
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| Burlington, : Elsevier Science, 1981 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Thinking about nuclear power in post-Saddam Iraq
| Thinking about nuclear power in post-Saddam Iraq |
| Autore | Cigar Norman L |
| Pubbl/distr/stampa | [Place of publication not identified], : Strategic Studies Institute, 2010 |
| Descrizione fisica | 1 online resource (ix, 71 pages) |
| Disciplina | 333.792/40956 |
| Soggetto topico |
Nuclear energy - Public opinion - Iraq
Nuclear industry - Public opinion - Iraq Nuclear weapons - Public opinion - Iraq National security - Iraq Nuclear nonproliferation - Iraq Mechanical Engineering Engineering & Applied Sciences Nuclear Engineering |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto | Introduction. The terms of reference ; Research sources and methods -- Lobbying for atomic power. The economic argument ; National pride -- Nuclear weapons in Iraq's future? Assessing nuclear threats to Iraq ; Assessing other nuclear threats ; The Kurdish viewpoint ; The utility of nuclear weapons ; Marginal dissonant views ; Ethical perspectives ; Environmental considerations -- Prospects and implications. The near-term trajectory ; Rebuilding an infrastructure -- Conclusions -- Recommendations. |
| Record Nr. | UNINA-9910694431303321 |
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Cigar Norman L
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| [Place of publication not identified], : Strategic Studies Institute, 2010 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Zirconium in the nuclear industry : 15th international symposium
| Zirconium in the nuclear industry : 15th international symposium |
| Pubbl/distr/stampa | [Place of publication not identified], : ASTM International, 2009 |
| Disciplina | 621.48/332 |
| Collana | STP Zirconium in the nuclear industry |
| Soggetto topico |
Nuclear fuel claddings
Zirconium alloys Mechanical Engineering Engineering & Applied Sciences Nuclear Engineering |
| ISBN | 0-8031-8007-1 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Zirconium in the Nuclear Industry |
| Record Nr. | UNINA-9910164295503321 |
| [Place of publication not identified], : ASTM International, 2009 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Zirconium in the nuclear industry : eighth international symposium
| Zirconium in the nuclear industry : eighth international symposium |
| Pubbl/distr/stampa | [Place of publication not identified], : ASTM, 1989 |
| Disciplina | 621.48/33 |
| Collana | STP Zirconium in the nuclear industry |
| Soggetto topico |
Nuclear fuel claddings - Congresses
Zirconium alloys - Congresses Mechanical Engineering Engineering & Applied Sciences Nuclear Engineering |
| ISBN | 0-8031-5084-9 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Zirconium in the Nuclear Industry |
| Record Nr. | UNINA-9910164315503321 |
| [Place of publication not identified], : ASTM, 1989 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Zirconium in the nuclear industry : fourteenth international symposium
| Zirconium in the nuclear industry : fourteenth international symposium |
| Pubbl/distr/stampa | [Place of publication not identified], : ASTM, 2006 |
| Disciplina | 621.48/332 |
| Collana | STP Zirconium in the nuclear industry |
| Soggetto topico |
Nuclear fuel claddings
Zirconium alloys Mechanical Engineering Engineering & Applied Sciences Nuclear Engineering |
| ISBN | 0-8031-5519-0 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910164299703321 |
| [Place of publication not identified], : ASTM, 2006 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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