Large-scale demonstration of barrier fuel in the Quad Cities Unit 2 Nuclear Power Station
Technical Report
·
OSTI ID:5145248
LWR nuclear fuel is susceptible to pellet cladding interaction (PCI) failures when subjected to fast power increases at moderate to high exposures. Zirconium barrier fuel was invented as a material solution to the PCI failure problem. This report describes the results of large-scale demonstrations of Zr-barrier fuel in the Quad Cities Unit 2 reactor. The demonstrations involved fast power increases on 16 bundles caused by stepwise (6 pulls) withdrawal of adjacent control blades. The first demonstration was performed in March 1983 at approximately 6 GWd/MTU and the fuel was subjected to power increases of up to 10 kW/ft to peak power levels of 12.6 kW/ft. The second demonstration was completed in March 1985 at an exposure of about 15 GWd/MTU. Peak power levels up to 13.7 kW/ft were achieved. All the ramped fuel was sound, both from plant offgas measurements and by fuel sipping.
- Research Organization:
- General Electric Co., San Jose, CA (USA). Nuclear Energy Business Operations
- DOE Contract Number:
- AC02-77ET34001
- OSTI ID:
- 5145248
- Report Number(s):
- NEDO-30967; ON: DE85016089
- Country of Publication:
- United States
- Language:
- English
Similar Records
Operational experience with zirconium-barrier fuel during cycle 8 of Quad Cities Unit 2
Demonstration of fuel resistant to pellet-cladding interaction. First semiannual report, July-December 1977
Demonstration of fuel resistant to pellet-cladding interaction: Phase 2. Fourth semiannual report, July-December 1980. [BWR]
Conference
·
Tue Dec 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6754867
Demonstration of fuel resistant to pellet-cladding interaction. First semiannual report, July-December 1977
Technical Report
·
Tue Jan 31 23:00:00 EST 1978
·
OSTI ID:5518260
Demonstration of fuel resistant to pellet-cladding interaction: Phase 2. Fourth semiannual report, July-December 1980. [BWR]
Technical Report
·
Sat Feb 28 23:00:00 EST 1981
·
OSTI ID:6278671
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
DEMONSTRATION PROGRAMS
ELEMENTS
ENRICHED URANIUM REACTORS
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
LAYERS
METALS
PERFORMANCE TESTING
POWER REACTORS
QUAD CITIES-2 REACTOR
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
TESTING
TRANSITION ELEMENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
DEMONSTRATION PROGRAMS
ELEMENTS
ENRICHED URANIUM REACTORS
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
LAYERS
METALS
PERFORMANCE TESTING
POWER REACTORS
QUAD CITIES-2 REACTOR
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
TESTING
TRANSITION ELEMENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM