Microstructural characterization of a thin film ZrN diffusion barrier in an As-fabricated U–7Mo/Al matrix dispersion fuel plate

• Published in: Journal of nuclear materials 2015-03, Vol.458 (C), p.406-418
• Main Authors: Keiser, Dennis D., Perez, Emmanuel, Wiencek, Tom, Leenaers, Ann, Van den Berghe, Sven
• Format: Article
• Language: English
• Subjects: Aluminum; Aluminum base alloys; Chemical Properties; Coating; CORROSION RESISTANCE; DENSITY; DEPOSITION; DIFFUSION BARRIERS; Dispersions; Electric Conductivity; Electrical Properties; FCC LATTICES; FRICTION; FUEL PLATES; Fuels; HARDNESS; IRRADIATION TESTING; LATTICE PARAMETERS; Mechanical Properties; MELTING POINTS; MICROSTRUCTURE; Nuclear engineering; NUCLEAR FUEL; NUCLEAR FUEL CYCLE AND FUEL MATERIALS; OPTIMIZATION; Plating; RESEARCH REACTOR; STABILITY; Temperature Range 1000-4000 K; THERMAL EXPANSION; Thermodynamic Properties; THIN FILMS; Uranium base alloys; URANIUM MOLYBDENUM ALLOY; ZIRCONIUM NITRIDES
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2014.12.036

The United States High Performance Research Reactor Fuel Development program is developing low enriched uranium fuels for application in research and test reactors. One concept utilizes U–7wt.% Mo (U–7Mo) fuel particles dispersed in Al matrix, where the fuel particles are coated with a 1μm-thick ZrN coating. The ZrN serves as a diffusion barrier to eliminate a deleterious reaction that can occur between U–7Mo and Al when a dispersion fuel is irradiated under aggressive reactor conditions. To investigate the final microstructure of a physically-vapor-deposited ZrN coating in a dispersion fuel plate after it was fabricated using a rolling process, characterization samples were taken from a fuel plate that was fabricated at 500°C using ZrN-coated U–7Mo particles, Al matrix and AA6061 cladding. Scanning electron and transmission electron microscopy analysis were performed. Data from these analyses will be used to support future microstructural examinations of irradiated fuel plates, in terms of understanding the effects of irradiation on the ZrN microstructure, and to determine the role of diffusion barrier microstructure in eliminating fuel/matrix interactions during irradiation. The as-fabricated coating was determined to be cubic-ZrN (cF8) phase. It exhibited a columnar microstructure comprised of nanometer-sized grains and a region of relatively high porosity, mainly near the Al matrix. Small impurity-containing phases were observed at the U–7Mo/ZrN interface, and no interaction zone was observed at the ZrN/Al interface. The bonding between the U–7Mo and ZrN appeared to be mechanical in nature. A relatively high level of oxygen was observed in the ZrN coating, extending from the Al matrix in the ZrN coating in decreasing concentration. The above microstructural characteristics are discussed in terms of what may be most optimal for a diffusion barrier in a dispersion fuel plate application.