Comparison between Canadian probabilistic safety assessment methods formulated by Atomic Energy of Canada limited and probabilistic risk assessment methods
The procedures used by Atomic Energy of Canada Limited (AECL) to perform probabilistic safety assessments (PRAs) differ somewhat from conventionally accepted probabilistic risk assessment (PRA) procedures used elsewhere. In Canada, PSA is used by AECL as an audit tool for an evolving design. The purpose is to assess the safety of the plant in engineering terms. Thus, the PSA procedures are geared toward providing engineering feedback so that necessary changes can be made to the design at an early stage, input can be made to operating procedures, and test and maintenance programs can be optimized in terms of costs. Most PRAs, by contrast, are performed in plants that are already built. Their main purpose is to establish the core melt frequency and the risk to the public due to core melt. Also, any design modification is very expensive. The differences in purpose and timing between PSA and PRA have resulted in differences in methodology and scope. The PSA procedures are used on all plants being designed by AECL.
- Research Organization:
- Atomic Energy of Canada Ltd., Sheridan Park, ON (Canada). CANDU Operations
- OSTI ID:
- 5767228
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 84:3; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220200 -- Nuclear Reactor Technology-- Components & Accessories
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
CANADA
COMPARATIVE EVALUATIONS
DESIGN
ENGINEERING
FEEDBACK
MAINTENANCE
MELTING
NORTH AMERICA
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PHASE TRANSFORMATIONS
POWER PLANTS
PROBABILISTIC ESTIMATION
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY EXPERIMENTS
RISK ASSESSMENT
THERMAL POWER PLANTS