Constituent migration model for U-Pu-Zr metallic fast reactor fuel
- Hitachi, Ltd., Ibaraki (Japan)
- Electric Power Industry, Tokyo (Japan)
A model for constituent migration behavior in U-Pu-Zr metallic fast reactor fuel is proposed. It is based on diffusion equations for the ternary system under a radial temperature gradient, and it takes into account the alloy phase decomposition, assuming a quasi-binary U-Zr phase diagram with a constant plutonium content. Parametric simulations of Experimental Breeder Reactor II irradiation data with appropriate transport properties of the alloy system showed that the model can predict the experimentally observed radial three-zone structure and zirconium and uranium redistribution, although the predicted radial location of zirconium-depleted middle zone disagreed with the experimental result. Accumulation of basic experimental data on transport properties and a ternary phase diagram of the system are needed for a better understanding of the behavior.
- OSTI ID:
- 5889761
- Journal Information:
- Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 104:1; ISSN 0029-5450; ISSN NUTYBB
- Country of Publication:
- United States
- Language:
- English
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210500* -- Power Reactors
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ACTINIDE ALLOYS
ALLOY NUCLEAR FUELS
ALLOYS
BREEDER REACTORS
DIAGRAMS
DIFFERENTIAL EQUATIONS
DIFFUSION
EBR-2 REACTOR
ENERGY SOURCES
EPITHERMAL REACTORS
EQUATIONS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCTS
FUELS
IRRADIATION
ISOTOPES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
MATHEMATICAL MODELS
NEUTRON DIFFUSION EQUATION
NUCLEAR FUELS
PHASE DIAGRAMS
PHYSICAL RADIATION EFFECTS
PLUTONIUM ALLOYS
POWER REACTORS
RADIATION EFFECTS
RADIOACTIVE MATERIALS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
SOLID FUELS
TEMPERATURE GRADIENTS
URANIUM ALLOYS
ZIRCONIUM ALLOYS