Fuel-cladding mechanical interaction in PCI-resistant LWR fuel designs during normal operation and power ramping
The fuel cladding mechanical interaction behavior of developmental fuel rods irradiated in the Halden Boiling Water Reactor was evaluated based primarily on rod elongation measurements made during steadystate and power-ramping irradiation. The developmental fuel rod designs were selected based on attributes that were expected to reduce pellet-cladding interaction (PCI) failures during irradiation. Testing results were compared to a nonpressurized reference design with dished-pellet fuel. For the reference rods, there was a relationship between thermal feedback and fuelcladding mechanical interaction during steady-state irradiation. Significant cladding stresses developed in both the axial and hoop directions in the reference rods during power ramping. During power ramping the general cladding stress distribution in fuel rods with annular fuel pellets was primarily axial while cladding stresses in rods with sphere-pac fuel were mostly in the hoop direction. These results are indicative of superior PCI resistance in the annular pellet fuel rod designs when compared to the reference and sphere-pac rods.
- Research Organization:
- Pacific-Northwest Laboratory, Richland, WA
- OSTI ID:
- 6477602
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 63:1; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
Similar Records
FUEL PERFORMANCE IMPROVEMENT PROGRAM Power-Ramp Testing and Postirradiation Examination of PCI-Resistant LWR Fuel Rod Designs
Fuel performance improvement program. Quarterly/annual progress report, October 1978-September 1979
Related Subjects
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
ACCIDENTS
ANNULAR FUEL ELEMENTS
BHWR TYPE REACTORS
DIMENSIONS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EXCURSIONS
EXPERIMENTAL REACTORS
FUEL CANS
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
HBWR REACTOR
HEAT TRANSFER
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
PHYSICAL RADIATION EFFECTS
POWER REACTORS
RADIATION EFFECTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
STEADY-STATE CONDITIONS
STRESS ANALYSIS
STRESSES
TANK TYPE REACTORS
TEMPERATURE EFFECTS
THERMAL REACTORS