Fuel swelling due to retained fission gas in molten fuel during high temperature transients
Fuel swelling, which caused cladding plastic strain, occurred within the film boiling region of previously irradiated pressurized-water-reactor-type fuel rods tested under power-cooling-mismatch conditions in the Power Burst Facility. Mechanisms contributing to the observed swelling are assessed and the applicability of an analytical fission gas behavior computer code, GRASS-SST, is evaluated. Fuel melting and expansion, expansion of the solid fuel, fission gas bubble coalescence, fission gas diffusion to grain boundaries, and decrease in surface tension of fuel upon melting were found to be the major contributors to the fuel swelling. In addition, the contribution to fuel swelling of solid fission products and the effects of cladding contraction and wall thinning on rod swelling were included in the fuel swelling calculations. The overall empiricallly calculated fuel swelling values and the GRASS-SST code calculated values were compared with measured values.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 5670590
- Report Number(s):
- NUREG/CR-1236; EGG-2014
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fission gas induced fuel swelling in low and medium burnup fuel during high temperature transients. [PWR]
GRASS-SST: A Comprehensive, Mechanistic Model for the Prediction of Fission-gas Behavior in UO2-base Fuels during Steady-state and Transient Conditions
Development and verification of the LIFE-GCFR computer code for predicting gas-cooled fast-reactor fuel-rod performance
Conference
·
Mon Dec 31 23:00:00 EST 1979
·
OSTI ID:5493761
GRASS-SST: A Comprehensive, Mechanistic Model for the Prediction of Fission-gas Behavior in UO2-base Fuels during Steady-state and Transient Conditions
Technical Report
·
Wed May 31 20:00:00 EDT 1978
·
OSTI ID:6556805
Development and verification of the LIFE-GCFR computer code for predicting gas-cooled fast-reactor fuel-rod performance
Technical Report
·
Sun Feb 28 23:00:00 EST 1982
·
OSTI ID:7095358
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
CRYSTAL STRUCTURE
FISSION PRODUCTS
FUEL ELEMENTS
FUEL RODS
ISOTOPES
MICROSTRUCTURE
MOCKUP
POWER-COOLING-MISMATCH ACCIDENTS
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
STRUCTURAL MODELS
SWELLING
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
CRYSTAL STRUCTURE
FISSION PRODUCTS
FUEL ELEMENTS
FUEL RODS
ISOTOPES
MICROSTRUCTURE
MOCKUP
POWER-COOLING-MISMATCH ACCIDENTS
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
STRUCTURAL MODELS
SWELLING
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS