Development and validation of Alfus: An irradiation behavior Analysis code for metallic Fast reactor fuels

摘要

An irradiation behavior analysis code for metallic fast reactor fuel, ALFUS, has been revised so that it can be applied to stress-strain analysis of U-Pu-Zr ternary fuel pins. The stress-strain calculation in ALFUS is closely coupled with models for slug deformation mechanisms, such as swelling due to accumulation of fission gas bub- bles and nongaseous fission products. These models in- clude the key parameters: threshold gas swelling for open pore formation, compressibility of the open pores, and accumulation rate of nongaseous fission products.