Investigation of the fueling machine availability for CANDU PHWRs
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5062768
None
- Research Organization:
- King Saud Univ., Riyadh
- OSTI ID:
- 5062768
- Report Number(s):
- CONF-850610-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 49
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AVAILABILITY
CANDU TYPE REACTORS
ENERGY TRANSFER
FAULT TREE ANALYSIS
FLUID MECHANICS
HEAT TRANSFER
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PHWR TYPE REACTORS
PRESSURE TUBE REACTORS
PROBABILISTIC ESTIMATION
REACTOR ACCIDENTS
REACTOR CHARGING MACHINES
REACTOR COMPONENTS
REACTOR FUELING
REACTOR SAFETY
REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AVAILABILITY
CANDU TYPE REACTORS
ENERGY TRANSFER
FAULT TREE ANALYSIS
FLUID MECHANICS
HEAT TRANSFER
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PHWR TYPE REACTORS
PRESSURE TUBE REACTORS
PROBABILISTIC ESTIMATION
REACTOR ACCIDENTS
REACTOR CHARGING MACHINES
REACTOR COMPONENTS
REACTOR FUELING
REACTOR SAFETY
REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS