METHOD OF FABRICATING A URANIUM-ZIRCONIUM HYDRIDE REACTOR CORE
A method is described of evenly dispersing uranlum metal in a zirconium hydride moderator to produce a fuel element for nuclear reactors. According to the invention enriched uranium hydride and zirconium hydride powders of 200 mesh particle size are thoroughly admixed to form a mixture containing 0.1 to 3% by weight of U/sup 235/ hydride. The mixed powders are placed in a die and pressed at 100 tons per square inch at room temperature. The resultant compacts are heated in a vacuum to 300 deg C, whereby the uranium hydride deoomposes into uranium metal and hydrogen gas. The escaping hydrogen gas forms a porous matrix of zirconium hydride, with uramum metal evenly dispersed therethrough. The advantage of the invention is that the porosity and uranium distribution of the final fuel element can be more closely determined and controlled than was possible using prior methods of producing such fuel ele- ments.
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-14-015973
- Assignee:
- U.S. Atomic Energy Commission
- Patent Number(s):
- US 2929707
- OSTI ID:
- 4183947
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
CARBON 14
CARBON DIOXIDE
COMBUSTION
COMPACTING
CONTROL
COUNTERS
DECOMPOSITION
DIES
DISPERSIONS
DISTRIBUTION
EFFICIENCY
FABRICATION
FUEL ELEMENTS
GASES
HEATING
HYDROGEN
METALS, CERAMICS, AND OTHER MATERIALS
MIXING
MODERATORS
POROSITY
POWDERS
PRESSURE
QUANTITATIVE ANALYSIS
REACTOR CORE
REACTORS
TEMPERATURE
TRITIUM
URANIUM
URANIUM 235
URANIUM HYDRIDES
VACUUM
WATER
ZIRCONIUM HYDRIDES