Thermal-hydraulic impact of failure of highly irradiated fuel pins on LMR passive safety
Conference
·
OSTI ID:6604427
The EBR-2 SHRT-45 loss-of-primary-flow-without scram test and SHRT 302 unprotected loss-of-heat-sink test have demonstrated that liquid metal reactors can be built with a high degree of passive safety. No fuel pins were observed to fail in these tests; but if the burnup of the fuel were pushed further, one would face the question of what could be the impact of pin failures and rapid release of plenum gas in such a transient. Also, there are questions about the impact of an unprotected rapid release of plenum gas following the failure of highly irradiated fuel during normal operation. One area of concern, and the one addressed in this document, is whether the release of gas from failed pins could interfere with the coolant flow enough to cause melting of the fuel, possibly leading to blockage of the coolant channels. To address this question, the coolant voiding model in the SASSYS-1 code was modified to account for voiding due to gas release from failed pins. This model was used to analyze both unprotected pin failures during normal operation and pin failures during a SHRT-45 type of unprotected loss-of-flow transient. 3 refs., 5 figs.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6604427
- Report Number(s):
- CONF-901101-17; ON: DE90013663
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPUTER CODES
COOLING SYSTEMS
EBR-2 REACTOR
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
FUEL CANS
FUEL ELEMENTS
FUEL PINS
GAS FLOW
HEAT TRANSFER
HYDRAULICS
IRRADIATION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
S CODES
SAFETY
SODIUM COOLED REACTORS
VOIDS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPUTER CODES
COOLING SYSTEMS
EBR-2 REACTOR
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
FUEL CANS
FUEL ELEMENTS
FUEL PINS
GAS FLOW
HEAT TRANSFER
HYDRAULICS
IRRADIATION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
S CODES
SAFETY
SODIUM COOLED REACTORS
VOIDS