URANIUM DIOXIDE FUEL MATERIALS WITH IMPROVED THERMAL CONDUCTIVITY

Technical Report · Mon Jun 01 04:00:00 EDT 1959

OSTI ID:4239626

Shapiro, H; Powers, R M

Metallic and ceramic materials were added to UO/sub 2/ fuel in thermal conductivity improvement experiments. Cermet type fuel cores with the framework consisting of Mo of Nb and UC/sub 2/ were prepared. These cermets are favorable for better heat transfer but are unfavorable with respect to their neutron economy. Small amounts of ceramic additions, such as the oxides of Y or Nb, which form solid solutions with UO/sub 2/, improved the thermal conductivity of the fuel material, with very little effect on neutron economy. The formation of these solid solutions, the thermal conductivity test equipment, and the test procedures are described, and the preliminary test results are discussed. (auth)

• Research Organization: Sylvania-Corning Nuclear Corp., Bayside, N.Y.
• NSA Number: NSA-13-017002
• OSTI ID: 4239626
• Report Number(s): SCNC-271
• Country of Publication: United States
• Language: English

Related Subjects

CERAMICS
CERMETS
FUELS
HEAT TRANSFER
LABORATORY EQUIPMENT
MATERIALS TESTING
METALLURGY AND CERAMICS
MOLYBDENUM
NEUTRONS
NIOBIUM
NIOBIUM OXIDES
SOLID SOLUTIONS
THERMAL CONDUCTIVITY
TRACE AMOUNTS
URANIUM DIOXIDE
YTTRIUM OXIDES