Fuel rod clip program at Duke Power's McGuire nuclear stations
Conference
·
· Transactions of the American Nuclear Society; (USA)
OSTI ID:7029481
During the Duke Power Company McGuire-1 end-of-Cycle-3 refueling outage, debris, including loose fuel pellets, were found. Duke Power determined that the debris resulted from three failed fuel rods from one peripheral assembly. The cladding of these three fuel rods had failed due to fretting resulting from baffle jetting. Prevention of further baffle-jetting damage was essential to forestall increased reactor and coolant contamination, maintain fuel assembly integrity, and minimize the impact on core operating power. Duke Power performed a study of possible methods of modifying a fuel assembly to eliminate baffle-jetting damage. The most promising approach was the proven fuel-rod clips designed by Advanced Nuclear Fuels Corporation (ANF) on assemblies exposed to baffle jetting. Installation of ANF fuel-rod clips in the McGuire-1 and McGuire-2 reactors by Duke Power has proven successful in eliminating baffle-jetting damage. Both reactors have operated one full cycle with ANF clips. No more baffle-jetting failures have been reported. Clip removal at the end of the cycle was carried out on schedule. Estimation of the clip removal force indicated the clips were firmly attached to the rods, thus confirming the adequacy of the clip design. Both reactors are now in their second cycle of operation with ANF clips.
- OSTI ID:
- 7029481
- Report Number(s):
- CONF-890604--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 59
- 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
ACCIDENTS
BAFFLES
CHEMICAL REACTIONS
CONTROL EQUIPMENT
COOLING SYSTEMS
CORROSION
DAMAGE
ENERGY SYSTEMS
ENERGY TRANSFER
EQUIPMENT
FASTENERS
FLOW REGULATORS
FLUID MECHANICS
FRETTING CORROSION
FUEL ASSEMBLIES
FUEL CANS
FUEL ELEMENT FAILURE
FUEL PELLETS
HEAT TRANSFER
HYDRAULICS
MC GUIRE-1 REACTOR
MC GUIRE-2 REACTOR
MECHANICS
OPERATION
PELLETS
POWER REACTORS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR FUELING
REACTOR OPERATION
REACTORS
REMOVAL
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACCIDENTS
BAFFLES
CHEMICAL REACTIONS
CONTROL EQUIPMENT
COOLING SYSTEMS
CORROSION
DAMAGE
ENERGY SYSTEMS
ENERGY TRANSFER
EQUIPMENT
FASTENERS
FLOW REGULATORS
FLUID MECHANICS
FRETTING CORROSION
FUEL ASSEMBLIES
FUEL CANS
FUEL ELEMENT FAILURE
FUEL PELLETS
HEAT TRANSFER
HYDRAULICS
MC GUIRE-1 REACTOR
MC GUIRE-2 REACTOR
MECHANICS
OPERATION
PELLETS
POWER REACTORS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR FUELING
REACTOR OPERATION
REACTORS
REMOVAL
WATER COOLED REACTORS
WATER MODERATED REACTORS