The motivation for exploring the potential development of accident tolerant fuels in light
water reactors to replace existing Zr alloy clad monolithic (U, Pu) oxide fuel is outlined. The …

UO 2 has a long history being used as a nuclear fuel. However, its low thermal conductivity
has become one of the major concerns limiting nuclear reactor performance and safety …

The challenges and opportunities to alloyed and composite fuel architectures designed and
intended to mitigate oxidation of the fuel during a cladding breech of a water-cooled reactor …

As one of accident tolerant fuel pellets which should have features of good thermal
conductivity and high fission product retention, a micro-cell UO 2–Mo pellet has been …

Qualification of new nuclear fuels is necessary for their deployment and requires a thorough
understanding of fuel behavior under irradiation. Traditionally, nuclear fuels have been …

Dense U 3 Si 2 pellets with controlled grain structure and enhanced thermal-mechanical
and oxidation properties are synthesized with spark plasma sintering (SPS). Microstructure …

Fabrication of monolithic UO 2 and UO 2-Mo composites from Mo metal powder feedstock
and UO 3 spheres derived from internal gelation was explored. The addition of 10 vol% Mo …

An investigation into the influence of processing parameters on densification of UO2 powder
during spark plasma sintering (SPS) is presented. A broad range of sintering temperatures …

Commercial SiC ceramics were joined by electric field-assisted sintering technology using a
Ti 3 SiC 2 (TSC) tape film. A SiC/TSC/SiC joining sample with bend strength of 80.4 MPa …

A robust solid state diffusion joining technique for SiC ceramics was designed with a
thickness-controlled Ti interlayer formed by physical vapor deposition and joined by electric …