Demonstration of fuel resistant to pellet-cladding interaction. Second semiannual report, January--June 1978. [BWR]
- comp.
This program has as its ultimate objective the demonstration of an advanced fuel concept that is resistant to the failure mechanism known as fuel pellet-cladding interaction (PCI). Since currently used fuel in the nuclear power industry is subject to the PCI failure mechanism, reactor operators limit the rates of power increases and thus reduce their capacity factors in order to protect the fuel. Two concepts are being developed for possible demonstration within this program: (a) Cu-barrier fuel and (b) Zr-liner fuel. These advanced fuels (known collectively as ''barrier fuels'') have special fuel cladding designed to protect the Zircaloy cladding tube from the harmful effects of localized stress and reactive fission products during reactor service. The demonstration of one of these concepts in a commercial power reactor is planned for PHASE 2 of this program. The current plans for the demonstration will involve approximately 132 bundles of PCI-resistant fuel.
- Research Organization:
- General Electric Co., San Jose, CA (USA). Nuclear Energy Engineering Div.
- OSTI ID:
- 6528952
- Report Number(s):
- GEAP-23773-1
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
ACTINIDE COMPOUNDS
ALLOYS
BWR TYPE REACTORS
CHALCOGENIDES
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
CONFIGURATION
COPPER
ELEMENTS
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
IRON ADDITIONS
IRON ALLOYS
METALS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
REACTOR COMPONENTS
REACTORS
TESTING
TIN ALLOYS
TRANSITION ELEMENTS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 2
ZIRCONIUM
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
ACTINIDE COMPOUNDS
ALLOYS
BWR TYPE REACTORS
CHALCOGENIDES
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
CONFIGURATION
COPPER
ELEMENTS
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
IRON ADDITIONS
IRON ALLOYS
METALS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
REACTOR COMPONENTS
REACTORS
TESTING
TIN ALLOYS
TRANSITION ELEMENTS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 2
ZIRCONIUM
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS