Fission gas behavior in mixed-oxide fuel during transient overpower and simulated loss-of-flow tests
A portion of the fission gases (Xe, Kr) generated during steady state irradiation of an FBR mixed-oxide fuel is retained within its microstructure, especially in the cooler regions of the fuel. Information on the behavior of these retained gases relative to their microstructural relocation and release during off-normal power and coolant flow conditions is important to the analysis and analytic modeling of fuel-pin transient and reactor core performance. This paper discusses the steady state and transient behavior of retained fission gas relative to the geometry, microstructure, temperature, and apparent release mechanisms within selected axial and radial regions of fuel pins irradiated at medium power (7 to 10 kW/ft) and burnup (30 to 60 MWd/kgm). The specific fuel pins are from the PNL-10 and PNL-2 subassemblies irradiated in EBR-II. The transient overpower tests involved integral fuel pin static capsule experiments performed in TREAT. Loss-of-coolant flow was simulated in an out-of-reactor thermal transient testing system using axial segments of irradiated fuel pins.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- EY-76-C-14-2170
- OSTI ID:
- 6265386
- Report Number(s):
- HEDL-SA-1552-S; CONF-790306-23
- Resource Relation:
- Conference: International conference on fast breeder reactor performance, Monterey, CA, USA, 5 Mar 1979
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FBR TYPE REACTORS
LOSS OF FLOW
TRANSIENT OVERPOWER ACCIDENTS
FUEL ELEMENTS
FISSION PRODUCT RELEASE
GASES
PLUTONIUM DIOXIDE
URANIUM DIOXIDE
ACCIDENTS
ACTINIDE COMPOUNDS
BREEDER REACTORS
CHALCOGENIDES
EPITHERMAL REACTORS
FAST REACTORS
FLUIDS
OXIDES
OXYGEN COMPOUNDS
PLUTONIUM COMPOUNDS
PLUTONIUM OXIDES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM OXIDES
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
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