Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Nuclear Fuel Research Fuel Cycle Development Program, Quarterly Progress Report, January 1 to March 31, 1961

Technical Report ·
DOI:https://doi.org/10.2172/4843266· OSTI ID:4843266

The laboratory scale development phase of a process for the fabrication of UO2 pellets based on low temperature sintering in nitrogen was completed. Work was initiated on the preparation and encapsulation of enriched UO2 pellets for irradiation testing. Further investigation of the effect of fluoride additions on the sintering behavior of UO2 con firmed that oxidation-reduction cycling restored the oxide sinterability lost as a result of fluoridation. A series of sintering experiments were performed with the objective of producing high density UO2 pellets in excess of 98 percent theoretical density. Modification of the oxidation-reduction activation treatment could produce such densities. It also appeared that sintering temperatures as low as 100 deg C can be used to prepare pellets of the design density of 95 percent theoretical density. The propane reaction was further studied to develop techniques for preparing uranium carbide powder to a given total carbon specification. A comparison was made between the use of unreacted UO2-graphite and reacted UO2-graphite charges to the arc skull furnace. The reacted charge gave the best results. The determination of the physical properties of uranium carbide as a function of composition and fabricational variables was initiated. The thermal expansion of cast 4.85 wt% C uranium carbide was determined at 12.55 x 10-6 in./in./°C.

Research Organization:
Olin Mathieson Chemical Corp., New Haven, CT (United States)
Sponsoring Organization:
US Atomic Energy Commission (AEC)
DOE Contract Number:
AT(30-1)-2374
NSA Number:
NSA-15-028744
OSTI ID:
4843266
Report Number(s):
NYO--2692
Country of Publication:
United States
Language:
English