DEVELOPMENT OF URANIUM MONONITRIDE. Quarterly Progress Report No. 3 for period ending June 30, 1961

Technical Report · Wed Oct 31 04:00:00 EST 1962

OSTI ID:4817840

Keller, D L

Work is being carried out to establish the feasibility of UN as a reactor fuel material. Fabrication was completed on all planned irradiation specimens. Thermal conductivity and electrical resistivity were measured in vacuum on a UN specimen over the temperature range 200 to 800 deg C. Dense UN specimens were exposed to 500 deg F deionized and degassed water for up to 14 days. The chemical corrosion that occured was apparently a surface reaction, and the material showed fairly good resistance to corrosion. Values for the solubility of H/sub 2/in UN were measured at 1 atm and 300 to 800 deg C. Melting and casting of UN was carried out. (M.C.G.)

• Research Organization: Battelle Memorial Inst., Columbus, Ohio
• DOE Contract Number: W-7405-ENG-92
• NSA Number: NSA-16-019347
• OSTI ID: 4817840
• Report Number(s): EURAEC-77
• Country of Publication: United States
• Language: English

Related Subjects

CASTING
CHEMICALS
CORROSION
ELECTRIC CONDUCTIVITY
FABRICATION
FUEL ELEMENTS
GASES
HYDROGEN
IONIZATION
IRRADIATION
MEASURED VALUES
MELTING
METALS, CERAMICS, AND OTHER MATERIALS
REACTION KINETICS
REACTORS
SOLUBILITY
SURFACES
TEMPERATURE
THERMAL CONDUCTIVITY
URANIUM NITRIDES
VACUUM
WATER