Development of annular-coated-pressurized and sphere-pac LWR fuels
Conference
·
OSTI ID:5338005
Annular-coated (graphite)-pressurized and sphere-pac fuel rod designs, which are expected to exhibit improved PCI-failure resistance, and, thus, more reliable extended burnup performance, are being developed. Data sufficient to provide the technical bases needed to license lead test assemblies of the improved designs for irradiation in commercial LWRs are being obtained. Out-of-reactor experiments, in-reactor instrumented experiments, in-reactor power-ramp tests, and lead-rod demonstration irradiations are providing the needed data to support the technical bases. Results obtained to-date confirm the expected performance improvement compared with a solid-pellet reference design. The degree of improvement with respect to PCI-resistance remains to be quantified during forthcoming power-ramp tests on fuel rod segments irradiated to moderate burnup levels in a commercial LWR.
- Research Organization:
- Consumers Power Co., Jackson, MI (USA); Exxon Nuclear Co., Inc., Richland, WA (USA); Battelle Pacific Northwest Labs., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5338005
- Report Number(s):
- PNL-SA-10104; CONF-820417-1; ON: DE82011231
- Country of Publication:
- United States
- Language:
- English
Similar Records
Thermal performance of annular-coated and sphere-pac LWR fuel rod designs
Fuel-cladding mechanical interaction in PCI-resistant LWR fuel designs during normal operation and power ramping
Fuel-cladding mechanical interaction in PCI-resistant LWR fuel designs during normal operation and power ramping
Conference
·
Mon Dec 31 23:00:00 EST 1979
·
OSTI ID:6881846
Fuel-cladding mechanical interaction in PCI-resistant LWR fuel designs during normal operation and power ramping
Journal Article
·
Sat Oct 01 00:00:00 EDT 1983
· Nucl. Technol.; (United States)
·
OSTI ID:6477602
Fuel-cladding mechanical interaction in PCI-resistant LWR fuel designs during normal operation and power ramping
Journal Article
·
Sat Oct 01 00:00:00 EDT 1983
· Nucl. Technol.; (United States)
·
OSTI ID:7144794
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
ANNULAR FUEL ELEMENTS
BWR TYPE REACTORS
CARBON
ELEMENTAL MINERALS
ELEMENTS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
FUEL PELLETS
FUEL RODS
FUEL-CLADDING INTERACTIONS
GRAPHITE
MINERALS
NONMETALS
PELLETS
PERFORMANCE TESTING
PHYSICAL PROPERTIES
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
TESTING
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ANNULAR FUEL ELEMENTS
BWR TYPE REACTORS
CARBON
ELEMENTAL MINERALS
ELEMENTS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
FUEL PELLETS
FUEL RODS
FUEL-CLADDING INTERACTIONS
GRAPHITE
MINERALS
NONMETALS
PELLETS
PERFORMANCE TESTING
PHYSICAL PROPERTIES
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
TESTING
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
WATER COOLED REACTORS
WATER MODERATED REACTORS