A thermodynamic approach for advanced fuels of gas-cooled reactors

Thermodynamic study of the U–Si system

“…For the Gas-cooled Fast Reactor, the carbides (U, Pu)C and SiC are considered as candidate materials for respectively the fuel kernel and the inert matrix [1][2][3]. The high level of the operating temperature of the fuel materials requires the prediction of the phase diagrams and the thermodynamic properties of the UPu-Si-C quaternary system.…”

Critical evaluation and thermodynamic optimization of the (U + Bi), (U + Si) and (U + Sn) binary systems

“…These investigations focus not only on the U-containing compounds used in the fuels, but also on the alloys of U with common elements of structural materials and fission products [1][2][3][4]. (U + Bi) and (U + Sn) molten alloys used as mixed fuel have been investigated by many researchers because of their notable advantages such as high specific power, low costs, better neutron economy, etc.…”

“…Reliable data of thermodynamic properties and phase transformations of (U + Sn) molten alloys in the extracting process are important for keeping the fuel reactor operating safely. Si, C and Si-C based alloys are candidates for the inert matrix in gas-cooled fast reactor [1,10]. For the design of optimal operation condition of fuel reactor with molten fuel containing (U + Si), a systematic knowledge of the phase equilibria and thermodynamic properties of (U + Si) alloys is required.…”

Thermodynamic study of the uranium–vanadium system

“…For the Gas-cooled fast reactor, the reference fuel materials are the mixed carbide (U, Pu)C as fuel kernel and SiC as cladding material [1]. To ensure the tightness towards the release of the gaseous fission products, a liner material made of refractory alloys may be inserted between the fuel kernel and the silicon carbide (SiC).…”