NUCLEAR FUEL RESEARCH FUEL CYCLE DEVELOPMENT PROGRAM QUARTERLY PROGRESS REPORT, APRIL 1-JUNE 30, 1961
- Published
- United States : [publisher not identified], 1961.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1961. - Physical Description
- microopaque : positive ; 8 x 13 cm
- Summary
- The fabrication and encapsulation of 41.95% enriched UO/sub 2/ pellets, preparatory to irradiation testing, is described. The pellets are produced by sintering in N/sub 2/ or H/sub 2/ at 1000 to 1300 deg C, with initial grain sizes of 5 to 10 mu ; pellet densities of 95 to 98% of the theoretical density are produced. The O/U ratio of the pellets is determined, and their microstructure is investigated. The effects of processing variables on the final grain sizes and on the removal of fluoride impurities are examined. A method is described by which the C content in UC may be controlled to plus or minus 0.1 wt%. The sintering characteristics of 1.0 to 4.7 464 carbon in UC at 1200 to 1800 deg C are studied. The consolidation of UC by skull melting is also considered. (T.F.H.)
- Report Numbers
- NYO-2693
- Other Subject(s)
- Canning
- Carbon
- Control
- Density
- Environment
- Fabrication
- Fluorides
- Grain size
- High temperature
- Hydrogen
- Impurities
- Irradiation
- Melting
- Metallography
- Metals, ceramics, and other materials
- Nitrogen
- Oxygen
- Pellets
- Preparation
- Quantity ratio
- Separation processes
- Sintering
- Solidification
- Testing
- Uranium carbides
- Uranium dioxide
- Uranium
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- DOE contract number: AT(30-1)-2374
NSA number: NSA-15-032503
OSTI Identifier 4824318
Research organization: United Nuclear Corp. Fuels Div., New Haven.
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