|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors V
||Mechanical Properties of Materials and Phases Relevant to Monolithic U-Mo Fuel System
||Ryan Newell, Dennis D. Keiser, Yongho Sohn
|On-Site Speaker (Planned)
The Materials Management and Minimization program (M3) is a global initiative to reduce the use of highly enriched uranium in modern nuclear reactors. Critical to the integrity of fuel system is the mechanical behavior of the materials involved. Materials commonly utilized in monolithic fuel plates include U-Mo fuel alloys, Zr diffusion barrier, Al cladding, and phases that evolve due to interdiffusion and reaction among the respective components. Through nano-indentation testing, hardness and reduced modulus values were systematically investigated with variation in fabrication parameters relevant for the monolithic fuel plates. A significant solid solution strengthening effect in U-Mo alloys is reported along with high hardness and elastic modulus of intermetallic compounds Al3Zr, Mo2Zr, among others) that form due to interdiffusion and reaction.
||Planned: A print-only volume