摘要: |
Advanced cladding materials are being considered for high-temperature applications in Generation IV reactors (e.g. T91, ODS steels). These materials provide better mechanical properties (e.g., creep strength) at these higher temperatures than the more commonly employed cladding steels (e.g., HT-9). However, consideration must also be given to other high-temperature phenomenon besides just the mechanical properties of the cladding when using fuels at high temperatures. In particular, the compatibility of the fuel and cladding must be considered. In Sodium Fast Reactors (SFRs) that employ metallic fuel, interactions of fuel and cladding (FCI) during irradiation of a fuel element can result in the formation of strength-reducing zones or possibly the formation of low melting phases [1]. This paper reports the results of diffusion experiments that were conducted with metallic fuel and advanced cladding materials at the relatively high temperature of 700 C. |