Solidus and liquidus temperatures in the uranium-plutonium-zirconium system
Renewed interest in metallic fuel for nuclear reactors has prompted study of the solidus and liquidus for the uranium-plutonium-zirconium system. These temperatures are of importance in assessing the possibility of fuel melting during abnormal reactor conditions. Data obtained in previous work in this area were found to be inadequate for the needs of the current reactor development effort. A dual effort was undertaken to provide the needed data. These were (1) thermodynamic phase diagram analysis and calculation of the ternary solidus and liquidus surfaces and (2) experimental determination of solidus and liquidus temperatures for selected alloys. The methods used and results obtained are described.
- Research Organization:
- Argonne National Lab., IL (USA); Ecole Polytechnique, Montreal, Quebec (Canada)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5151692
- Report Number(s):
- CONF-8706258-4; ON: DE88010085
- Country of Publication:
- United States
- Language:
- English
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ACTINIDES
BREEDER REACTORS
CALCULATION METHODS
ELEMENTS
ENERGY SOURCES
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUIDS
FUELS
LIQUID METAL COOLED REACTORS
LIQUIDS
LMFBR TYPE REACTORS
MATERIALS
MELTING POINTS
METALS
NUCLEAR FUELS
PHYSICAL PROPERTIES
PLUTONIUM
REACTOR MATERIALS
REACTORS
SOLIDS
TEMPERATURE EFFECTS
THERMODYNAMIC PROPERTIES
TRANSITION ELEMENTS
TRANSITION TEMPERATURE
TRANSURANIUM ELEMENTS
URANIUM
ZIRCONIUM