Preliminary studies of used fuel generated in the US Department of Energy’s Advanced Fuel Cycle Initiative have indicated that current used fuel transport casks may be insufficient for the transportation of said fuel. This work considers transport of three 5-year-cooled oxide Advanced Burner Reactor used fuel assemblies with a burn-up of 160 MWD/kg. A transport cask designed to carry these asse...

During the exploitation of nuclear reactors, various U-Al based ternary intermetallides are formed in the fuel-cladding interaction layer. Structure and physical properties of these intermetallides determine the radiation resistance of cladding and, ultimately, the reliability and lifetime of the nuclear reactor. In current research, U(Al, Si)₃ composition was studied as a potential constituent...

A quenching experiment is performed to investigate the heat transfer characteristics and cooling performance of CrAl-coated Zircaloy (Zr) cladding in a water flow. The Zr one accident tolerant fuels for light reactors. uncoated also used this comparison. This simulates reflood fuel rod during loss coolant (LOCA) nuclear power plant. test conditions were determined represent peak temperature, su...

issues. These include the material employed in the reactor walls, the cladding material for the fissile nuclear fuel, and the material used for retaining the fission products. In addition to long term resistance to irradiation, the materials used in a nuclear reactor must have excellent mechanical and corrosion properties in order to tolerate the thermal shocks as well as the high temperature a...

Preliminary studies of used fuel generated in the US Department of Energy’s Advanced Fuel Cycle Initiative have indicated that current used fuel transport casks may be insufficient for the transportation of said fuel. This work considers transport of three 5-year-cooled oxide advanced burner reactor used fuel assemblies with a burn-up of 160 MWD kg. A transport cask designed to carry these asse...

Characterisation of materials utilised for fuel cladding in nuclear reactors prior to service is integral in order to understand corrosion mechanisms which would take place in reactor. Zircaloy-4 is one such material of choice for nuclear fuel containment in Pressurised Water Reactors (PWRs). In particular, the metal-oxide interface has been a predominant focus of previous research, however, du...

Phenomenon identification and ranking tables (PIRTs) were developed by an international group of fuel experts for three postulated accident types that are important in plant safety analysis. Rankings were determined with regard to cladding damage and fuel dispersal for high-burnup fuel rods. Developing PIRTs is a structured way of obtaining expert opinions to help improve computer codes and to ...