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ENGPHYS 713

Nuclear Safety Analysis and Reactor Accidents

Graduate

Winter 2026 · C01

Topics

  • Objectives of Safety Analysis, Types and Stages of Deterministic Safety Analysis
  • The concept of risk acceptability and the history of Probabilistic Safety Assessment in estimating the reliability of design requirements
  • The Plant Systems, Structures and Components Important to Safety and Barriers Preventing the Transmission of Radionuclides – Part 1
  • The Plant Systems, Structures and Components Important to Safety and Barriers Preventing the Transmission of Radionuclides – Part 2
  • Postulated Initiating Events (PIEs) and Acceptance Criteria for Design Basis Events
  • Accident Analysis – Part 1
  • Accident Analysis – Part 2
  • Accident Analysis – Part 3
  • Accident Analysis – Part 4
  • Beyond Design Basis Accidents (BDBA)
  • Severe Accidents
  • Reactor Accident Case Studies
Winter

Topics

  • Degraded fuel heat transfer
  • Fuel failure mechanisms
  • Fission product release and transport from nuclear fuel
  • Leak-before-break and piping fracture mechanics
  • Pipe ruptures
  • Challenges to containment system integrity
  • Severe accident progression and mitigation
  • Off-site release of fission products
  • Applications to CANDU and LWR reactors

Readings

  • The materials section states none.
    See source
Sources