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Reactor operation /
| Clasificación: | Libro Electrónico |
|---|---|
| Autor principal: | |
| Formato: | Electrónico eBook |
| Idioma: | Inglés |
| Publicado: |
Oxford ; New York :
Pergamon Press,
[1969]
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| Edición: | [1st ed.]. |
| Colección: | The Commonwealth and international library. Nuclear engineering division
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| Temas: | |
| Acceso en línea: | Texto completo |
Tabla de Contenidos:
- Front Cover; Reactor Operation; Copyright Page; Table of Contents; Preface; CHAPTER 1. General Problems of Reactor Operation; 1.1. INTRODUCTION; 1.2. AIMS OF REACTOR OPERATION; 1.3. ADMINISTRATION AND ORGANISATION; 1.4. SAFETY CONSIDERATIONS; 1.5. MAXIMUM CREDIBLE ACCIDENTS; 1.6. SITING REQUIREMENTS; 1.7. RULES AND LICENSING CONDITIONS; REFERENCES; CHAPTER 2. Principles of Control and Operation; 2.1. METHODS OF CONTROL; 2.2. RANGE OF CONTROL; 2.3. EFFECTIVENESS OF CONTROL ABSORBERS; 2.4. FLUX SHAPING; 2.5. TYPES OF CONTROL RODS; 2.6. THE EFFECTS OF CONTROL ROD WITHDRAWAL
- 2.7. FUNCTIONS OF OPERATORS2.8. LAYOUT OF CONTROL DESKS; 2.9. WARNINGS AND EMERGENCIES; 2.10. INTERLOCKS; 2.11. SAFETY LINES; REFERENCES; CHAPTER 3. Nuclear Instrumentation; 3.1. GENERAL PRINCIPLES; 3.2. RANGE OF MEASUREMENT; 3.3. POSITIONING OF INSTRUMENTS; 3.4. USE OF A NEUTRON SOURCE; 3.5. USE OF LEAD- SHIELDED IONISATION CHAMBERS; 3.6. TYPES OF INSTRUMENT FOR NEUTRON MEASUREMENT; 3.7. INSTRUMENTS ASSOCIATED WITH IONISATION CHAMBERS AND PULSE COUNTERS; 3.8. TYPICAL ARRANGEMENTS FOR REACTOR POWER INSTRUMENTATION; REFERENCES; CHAPTER 4. Reactor Start-up; 4.1. REACTOR START-UP SEQUENCE
- 4.2. TYPICAL START-UP SEQUENCE FOR A GAS-COOLED REACTOR4.3. THE IMPORTANCE OF A DUMP CONDENSER; 4.4. OVERALL STATION CONTROL8 ; 4.5. OVERALL CONTROL OF DIFFERENT TYPES OF REACTOR; 4.6. PROCEDURE FOR THE START-UP OF A GAS-COOLED NUCLEAR POWER STATION; REFERENCES; CHAPTER 5. Pre-Nuclear Commissioning; 5.1. MECHANICAL AND ELECTRICAL TESTS; 5.2. COOLANT FLOW TESTS; 5.3. GAS DISCHARGE FROM STACKS; REFERENCES; CHAPTER 6. Reactor Physics Experiments; 6.1. LOADING TO CRITICALITY; 6.2. SAFETY ASPECTS OF AN APPROACH TO CRITICALITY; 6.3. REACTOR PARAMETER MEASUREMENTS
- 6.4. THE ESTIMATION OF keff FOR THE FULLY LOADED REACTOR FROM ""JUST CRITICAL"" MEASUREMENTS6.5. LOADING TO FULL SIZE; REFERENCES; CHAPTER 7. Control Rod Calibrations and Temperature Coefficient Measurements; 7.1. DOUBLING TIME METHOD; 7.2. INTERCALIBRATION METHOD; 7.3. ROD DROP TECHNIQUE; 7.4. SOURCE JERK METHOD; 7.5. ROD OSCILLATOR TECHNIQUE; 7.6. PULSED NEUTRON SOURCE TECHNIQUE; 7.7. DISTRIBUTED POISON METHOD; 7.8. THE MEASUREMENT OF SHUT-DOWN CAPACITY; 7.9. TEMPERATURE COEFFICIENT MEASUREMENTS; REFERENCES; CHAPTER 8. Fuel Element Leak Detection and Fuel Movement; 8.1. INTRODUCTION
- 8.2. DETECTION BY FISSION PRODUCT GAMMA ACTIVITY8.3. DETECTION BY DELAYED NEUTRON EMISSION; 8.4. DETECTION BY BETA EMISSION; 8.5. DETECTION BY GASEOUS FISSION PRODUCT ACTIVITY; 8.6 THE WIRE PRECIPITATOR METHOD; 8.7. FUEL MOVEMENT; REFERENCES; CHAPTER 9. Operation at Power; 9.1. INTRODUCTION; 9.2. TEMPERATURE SURVEYS AND TEMPERATURE ASSESSMENT; 9.3. OPERATIONAL FLUX PLOTS; 9.4. REACTOR HEAT BALANCE; 9.5. XENON POISONING; 9.6. REACTIVITY EFFECTS DUE TO LONG-TERM CHANGES; 9.7. REACTIVITY BALANCE; 9.8. TEMPERATURE COEFFICIENTS; 9.9. CONTROL ROD CALIBRATIONS AT POWER; REFERENCES; Index