Nuclear Fuel Research Fuel Cycle Development Program: Quarterly Progress Report, April 1-June 30, 1961

Technical Report · Wed Aug 09 20:00:00 EDT 1961

DOI:https://doi.org/10.2172/4824318· OSTI ID:4824318

The fabrication and encapsulation of 41.95% enriched UO₂ pellets, preparatory to irradiation testing, is described. The pellets are produced by sintering in N₂ or H₂ 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.

• Research Organization: United Nuclear Corporation, New Haven, CT. Nuclear Fuel Research Laboratory
• Sponsoring Organization: US Atomic Energy Commission (AEC)
• DOE Contract Number: AT(30-1)-2374
• NSA Number: NSA-15-032503
• OSTI ID: 4824318
• Report Number(s): NYO--2693
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
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
URANIUM CARBIDES
URANIUM DIOXIDE