Demonstration of fuel resistant to pellet-cladding interaction. Phase I. Final report
- comp.
This program has as its ultimate objective the demonstration of an advanced fuel design that is resistant to the failure mechanism known as fuel pellet-cladding interaction (PCI). Two fuel 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. This is the final report for PHASE 1 of this program. Support tests have shown that the barrier fuel resists PCI far better than does the conventional Zircaloy-clad fuel. Power ramp tests thus far have shown good PCI resistance for Cu-barrier fuel at burnup > 12 MWd/kg-U and for Zr-liner fuel > 16 MWd/kg-U. The program calls for continued testing to still higher burnup levels in PHASE 2.
- Research Organization:
- General Electric Co., San Jose, CA (USA). Nuclear Energy Engineering Div.
- DOE Contract Number:
- EN-77-C-02-4473
- OSTI ID:
- 6019484
- Report Number(s):
- GEAP-23773-2
- 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
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210400 -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
ACTINIDE COMPOUNDS
ALLOYS
BWR TYPE REACTORS
CANDU TYPE REACTORS
CHALCOGENIDES
CRYSTAL STRUCTURE
FUEL CANS
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
HEAVY WATER MODERATED REACTORS
MICROSTRUCTURE
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PRESSURE TUBE REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
TESTING
THERMAL REACTORS
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210400 -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
ACTINIDE COMPOUNDS
ALLOYS
BWR TYPE REACTORS
CANDU TYPE REACTORS
CHALCOGENIDES
CRYSTAL STRUCTURE
FUEL CANS
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
HEAVY WATER MODERATED REACTORS
MICROSTRUCTURE
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PRESSURE TUBE REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
TESTING
THERMAL REACTORS
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS