TY - JOUR
T1 - Microstructural characterization of a thin film ZrN diffusion barrier in an as-fabricated U7Mo-Al matrix dispersion fuel plate
AU - Keiser, Dennis D.
AU - Perez, Emmanuel
AU - Wiencek, Tom
AU - Leenaers, Ann
AU - Van den Berghe, Sven
N1 - Score = 10
PY - 2015/1
Y1 - 2015/1
N2 - 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. 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. 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.
AB - 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. 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. 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.
KW - irradiation testing
KW - nuclear fuel
KW - research reactor
KW - uranium molybdenum alloy
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_137928
UR - http://knowledgecentre.sckcen.be/so2/bibref/12117
U2 - 10.1016/j.jnucmat.2014.12.036
DO - 10.1016/j.jnucmat.2014.12.036
M3 - Article
SN - 0022-3115
VL - 458
SP - 406
EP - 418
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
IS - 03
ER -