Degraded cooling in a CANDU reactor
Loss of coolant accident (LOCA) analysis for a Canada Deuterium Uranium (CANDU) reactor considers a wide range of postulated break sizes and locations in the heat transport piping. Coincident failure of the emergency coolant injection system to operate on demand must also be considered. The unique features of the CANDU core and heat transport system, and how these features affect the response of the system to a LOCA, are described. The possible range of behavior of the fuel and fuel channels following a LOCA is discussed in terms of the maximum fuel temperatures that could occur and also in terms of the potential for breaching the core pressure boundary (in the case of CANDU, this boundary comprises a large number of horizontal pressure tubes, each containing horizontal fuel bundles). It is concluded that fuel temperatures remain well below the UO/sub 2/ melting temperatures and that the integrity of the pressure tubes is maintained for all postulated LOCAs.
- Research Organization:
- Ontario Hydro, Toronto, Ontario
- OSTI ID:
- 6246435
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 88:3; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
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ACCIDENTS
ACTINIDE COMPOUNDS
CANDU TYPE REACTORS
CHALCOGENIDES
COOLING
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FUEL ASSEMBLIES
FUEL CHANNELS
FUEL ELEMENT CLUSTERS
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
LOSS OF COOLANT
MELTING POINTS
OXIDES
OXYGEN COMPOUNDS
PHYSICAL PROPERTIES
PRESSURE TUBE REACTORS
PRESSURE TUBES
REACTOR ACCIDENTS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR CORES
REACTOR PROTECTION SYSTEMS
REACTORS
TEMPERATURE EFFECTS
THERMAL REACTORS
THERMODYNAMIC PROPERTIES
TRANSITION TEMPERATURE
TUBES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES