DEVELOPMENT OF URANIUM MONONITRIDE. Quarterly Progress Report for July- September 1963

Technical Report · Tue Oct 01 04:00:00 EDT 1963

OSTI ID:4158829

Keller, D L

Uranium mononitride was fabricated by both powder and melting techniques. The probable source of the high oxygen content in uranium mononitride fabricated by powder techniques was traced to the powder preparation process. Tertative pressure-temperature diagrams for the uranium-nitrogen system were constructed. A solid solution was found between U/sub 2/N/sub 3/ and UN/sub 2/. Stoichiometric UN/sub 2/ exists only at very high pressures. Several types of UN, prepared by various fabrication techniques, are now being irradiated. The compatibility of UN with aluminum, Zircaloy-2, and type 304 stainless steel was checked to maximum temperatures of 600, 900, and 1350 deg C, respectively. A tentative reaction-rate curve was derived for the UN-- Zircaloy-2 system. Stoichiometric UN is resistant to corrosion by water at 300 deg C; hyperstoiyhiometric and hypstoichiometric UN are not. Weight gainversus-time curves for UN exposed to dry oxyge and carbon dioxide were obtained. (N.W.R.)

• Research Organization: Battelle Memorial Inst., Columbus, Ohio
• DOE Contract Number: W-7405-ENG-92
• NSA Number: NSA-18-000542
• OSTI ID: 4158829
• Report Number(s): BMI-X-10061; EURAEC-845
• Country of Publication: United States
• Language: English

Related Subjects

ALUMINUM
CARBON DIOXIDE
CORROSION
DIAGRAMS
FABRICATION
HIGH TEMPERATURE
IRRADIATION
MELTING
METALS, CERAMICS, AND OTHER MATERIALS
OXYGEN
PHASE DIAGRAMS
PLANNING
POWDERS
PREPARATION
PRESSURE
SOLID SOLUTIONS
STABILITY
STAINLESS STEEL- 304
STAINLESS STEELS
TEMPERATURE
URANIUM NITRIDES
WATER
WEIGHT
ZIRCALOY