Fission-gas-induced swelling in extended burnup fuel during high temperature transients
Conference
·
OSTI ID:5338722
Analyses of fission-gas-induced fuel swelling in low and medium burnup (7 to 16 GWd/tU) fuel tested under power-cooling-mismatch (PCM) conditions in the Power Burst Facility (PBF) have been extended to a high burnup (50 GWd/tU) pressurized-water-reactor-type commercial fuel rod. The fission-gas-induced fuel swelling and the total calculated swelling, which is the sum of swelling due to fission gases, thermal effects, and solid fission products, were 6 and 10.1%, respectively. The results suggest that fuel swelling due to retained fission gas during a high temperature PCM transient does not present a significant safety issue. To verify the analyses, consideration should be given to performing typical PBF PCM tests with extended burnup fuel.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5338722
- Report Number(s):
- EGG-M-00282; CONF-820472-1; ON: DE82017731
- Country of Publication:
- United States
- Language:
- English
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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
BURNUP
FISSION PRODUCTS
FUEL ELEMENTS
FUEL RODS
ISOTOPES
MATERIALS
POWER-COOLING-MISMATCH ACCIDENTS
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
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REACTOR COMPONENTS
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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
BURNUP
FISSION PRODUCTS
FUEL ELEMENTS
FUEL RODS
ISOTOPES
MATERIALS
POWER-COOLING-MISMATCH ACCIDENTS
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
SWELLING
WATER COOLED REACTORS
WATER MODERATED REACTORS