Design of the Reactor Containment and Associated Systems for Nuclear Power Plants Specific Safety Guide.

Detalles Bibliográficos
Clasificación:Libro Electrónico
Autor principal: IAEA
Formato: Electrónico eBook
Idioma:Inglés
Publicado: Havertown : International Atomic Energy Agency, 2019.
Colección:IAEA Safety Standards Ser.
Temas:
Nuclear power plants > Design and construction.
Centrales nucléaires > Conception et construction.
Nuclear power plants > Design and construction
Acceso en línea:Texto completo
Tabla de Contenidos:
  • Intro
  • 1. INTRODUCTION
  • Background
  • Objective
  • Scope
  • Structure
  • 2. CONTAINMENT SAFETY FUNCTIONS AND THE DESIGN APPROACH
  • Safety functions
  • Confinement of radioactive material
  • Protection against external and internal hazards
  • Radiation shielding
  • 3. DESIGN BASIS OF THE CONTAINMENT STRUCTURE AND ITS COMPONENTS AND ASSOCIATED SYSTEMS
  • General
  • Postulated initiating events
  • Internal hazards
  • External hazards
  • Accident conditions
  • General
  • Design basis accidents
  • Design extension conditions
  • Design limits
  • Reliability
  • Systems designed to mitigate design basis accidents
  • Safety features for design extension conditions without significant fuel degradation
  • Safety features for design extension conditions with core melting
  • Defence in depth
  • Practical elimination of conditions that could lead to an early radioactive release or a large radioactive release
  • Safety classification
  • Environmental qualification
  • Codes and standards
  • Use of probabilistic safety analyses in design
  • 4. Design of the containment and its associated systems
  • General
  • Layout and configuration of the containment and its associated systems
  • Maintenance and accessibility
  • Operator actions
  • Sharing of parts of the containment systems between units
  • Ageing effects
  • Decommissioning
  • Structural design of containment
  • General design process
  • Loads and load combinations
  • Engineering criteria
  • Local stresses and fatigue
  • Ultimate capability and failure mode
  • Structural design of structures within the containment
  • In-vessel retention strategy
  • Ex-vessel retention strategy
  • Structural design of systems
  • Mass and energy release and management
  • Control of pressure and temperature in operational states
  • Control of pressure and temperature in accident conditions
  • Control and limitation of radioactive releases
  • Containment source term
  • Leaktightness of the containment
  • Secondary confinement building
  • Containment bypass
  • Reduction of radioactive material in the containment atmosphere
  • Management of combustible gases
  • Generation of combustible gases
  • Threats due to combustible gases in design extension conditions with core melting
  • Measures for the mitigation of hydrogen combustion and for the prevention of hydrogen combustion challenging the containment integrity
  • Mechanical features of the containment
  • Provisions for containment isolation of piping and ducting systems
  • Isolation valves
  • Penetrations
  • Air locks, doors and hatches
  • Materials
  • Concrete
  • Metallic materials
  • Soft sealing materials
  • Covering, cushioning, thermal insulation and coating materials
  • Instrumentation
  • Monitoring the stability of the containment
  • Detection of deviations from normal operation

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