Abstract
The ultimate goal of simulating nuclear fuel is to predict a fuel rod’s behavior and lifetime in a reactor. Doing so requires taking into account the coupled effects of heat transfer, the mechanical interaction between the fuel and its surrounding protection, the isotopic evolution caused by the irradiation, and the chemical interactions between fuel, fission products, cladding, and coolant. In view of the strong interactions between the various aspects of fuel performance and the resulting mathematical problems, the simulation of the fuel behavior requires fuel performance codes, which are being used by safety authorities, research organizations, and fuel vendors. The basic equations for each aspect of the codes are described in this chapter, together with the specific features of and modeling requirements for the design basis accident analysis. Finally, this chapter also outlines the advanced issues and future needs of fuel performance codes for nuclear fuel rods based on oxides.
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