Manufacturability of U{sub 3}Si{sub 2} and its high temperature oxidation behaviour
High density fuels, such as uranium silicide (U{sub 3}Si{sub 2}), are being considered alongside improved cladding materials to develop new fuels which are both economic to manufacture and demonstrate enhanced accident tolerance. Through a collaborative programme led by Westinghouse and involving national laboratories in the US and UK, efforts are being made to establish a viable route by which U{sub 3}Si{sub 2} can be manufactured and to test its suitability as a fuel. In the UK work has focused on routes to convert UF{sub 6} and UF{sub 4} to U{sub 3}Si{sub 2} directly, without needing to reduce the uranium to its metallic state. Experimental observations of reactions between UF{sub 4} and Si indicate the formation of a USi{sub 2-x} phase at a temperature of 1000 C. degrees, consistent with thermodynamic assessments. Work on the construction of a rig which will pass UF{sub 6} heated to 1000 C. degrees through a bed of finely divided Si powder, is also reported. At Westinghouse, U{sub 3}Si{sub 2} fabricated by the arc-melting process has been subjected to high temperature steam and synthetic air tests and the reaction rate measured as a function of temperature using differential scanning calorimetry. The rates are compared to UO{sub 2} and UN (Uranium mononitride). At Idaho National Laboratory irradiation testing of U{sub 3}Si{sub 2} fuel is in progress. Fuel specimens were prepared by conventional arc melting process to formulate the U{sub 3}Si{sub 2} followed by conventional powder metallurgy processes to create pellets. These irradiation tests are intended to help resolve questions concerning the swelling of U{sub 3}Si{sub 2} under conditions representative of LWR fuel. (authors)