Unavailability assessment of the emergency core cooling system in a CANDU-PHWR
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6375388
None
- Research Organization:
- King Saud University, P.O. Box 800, Riyadh 11421
- OSTI ID:
- 6375388
- Report Number(s):
- CONF-841105-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 47
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210400 -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDES
CANDU TYPE REACTORS
CONTAINERS
CONTROL SYSTEMS
COOLANTS
COOLING SYSTEMS
ECCS
ELEMENTS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
FAILURES
HEAVY WATER
HEAVY WATER MODERATED REACTORS
HYDROGEN COMPOUNDS
LOSS OF COOLANT
METALS
OXYGEN COMPOUNDS
PRESSURE TUBE REACTORS
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR FUELING
REACTOR PROTECTION SYSTEMS
REACTORS
SAFETY INJECTION
SIGNALS
THERMAL REACTORS
URANIUM
WATER
210400 -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDES
CANDU TYPE REACTORS
CONTAINERS
CONTROL SYSTEMS
COOLANTS
COOLING SYSTEMS
ECCS
ELEMENTS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
FAILURES
HEAVY WATER
HEAVY WATER MODERATED REACTORS
HYDROGEN COMPOUNDS
LOSS OF COOLANT
METALS
OXYGEN COMPOUNDS
PRESSURE TUBE REACTORS
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR FUELING
REACTOR PROTECTION SYSTEMS
REACTORS
SAFETY INJECTION
SIGNALS
THERMAL REACTORS
URANIUM
WATER