Design of the Reactor Core for Nuclear Power Plants Specific Safety Guide.

Detalles Bibliográficos
Clasificación:Libro Electrónico
Autor Corporativo: International Atomic Energy Agency
Formato: Electrónico eBook
Idioma:Inglés
Publicado: Vienna : International Atomic Energy Agency, 2005.
Colección:Safety standards series ; no. NS-G-1.12.
Temas:
Nuclear reactors > Design and construction.
Nuclear power plants > Safety measures.
Réacteurs nucléaires > Conception et construction.
Centrales nucléaires > Sécurité > Mesures.
Nuclear power plants > Safety measures
Nuclear reactors > Design and construction
Acceso en línea:Texto completo
Tabla de Contenidos:
  • Intro
  • 1. INTRODUCTION
  • Background
  • Objective
  • Scope
  • Structure
  • 2. GENERAL SAFETY CONSIDERATIONS IN THE DESIGN of THE REACTOR CORE
  • Management system
  • Design objectives
  • Fundamental safety functions
  • Adequate design based on the concept of defence in depth
  • Proven engineering practices
  • Safety assessment in the design process
  • Features to facilitate radioactive waste management
  • Design basis for structures, systems and components of the reactor core
  • Plant states and postulated initiating events
  • External hazards
  • Design limits
  • Safety classification aspects of the reactor core
  • Engineering design rules
  • Design for reliability
  • Operational limits and conditions
  • Design for safe operation
  • Reactor core safety analysis
  • 3. SPECIFIC SAFETY CONSIDERATIONS IN THE DESIGN OF THE REACTOR CORE
  • General
  • Fuel type
  • Coolant
  • Moderator
  • Neutronic design
  • Design considerations
  • Nuclear design limits
  • Thermohydraulic design
  • Design considerations
  • Thermohydraulic design limits
  • Thermomechanical design of fuel rods and fuel assemblies
  • Design considerations
  • Fuel design limits
  • Mechanical design of core structures and components
  • Design considerations
  • Design limits for the mechanical design of core structures and components
  • Reactor core control, shutdown and monitoring systems
  • Reactor core control system
  • Reactor shutdown system
  • Partial trip system
  • Operating limits and set points
  • Core monitoring system
  • Core management
  • Design considerations
  • Core management design limits
  • Special core configurations
  • Impact of fuel design and core management on fuel handling, transport, storage, reprocessing and disposal
  • 4. QUALIFICATION AND TESTING
  • General
  • Design qualification
  • Inspection
  • Testing including prototype assemblies and lead use assemblies
  • REFERENCES
  • Annex ISUPPLEMENTARY TECHNICAL INFORMATION
  • Annex II ASPECTS TO BE ADDRESSED IN THE DESIGN OF THE FUEL ROD, FUEL ASSEMBLY, REACTIVITY CONTROL ASSEMBLY, NEUTRON SOURCE ASSEMBLY AND HYDRAULIC PLUG ASSEMBLY
  • CONTRIBUTORS TO DRAFTING AND REVIEW

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