Prediction of a contact induced failure of an SFR fuel rod end cap using an acceleration test

Contact induced failure of a sodium cooled fast reactor fuel rod is considered in this paper. An acceleration test is conducted with the specimens of actual dimensions and material to predict the maintainability of the structural and functional integrity until the end of the fuel life. Finite element analyses are carried out to obtain the vibration and contact characteristics of the relevant components. The test time is determined as 16.5 h by consulting the reliability engineering. Neither a wear nor a fatigue crack is found on any contact surface of the five specimens tested. This is interpreted as the end cap of the fuel rod would guarantee the B0.004 life with 99% reliability.