Irradiation behavior analyses of MA bearing oxide fuel pin for sodium-cooled fast reactors

Mizuno, Tomoyasu; Koyama, Shinichi  ; Kaito, Takeji ; Uwaba, Tomoyuki ; Tanaka, Kenya

As a fuel concept for commercialized Sodium-cooled fast reactor (SFR) system, minor actinides (MA) bearing oxide fuel with oxide dispersion strengthened martensitic steel (ODS) cladding was considered under homogeneous TRU recycling strategy. The MA content is calculated to be around 5% of heavy metal in case of trans-uranium (TRU) feed from light water reactor (LWR) spent fuel during the transition phase from LWR to fast reactor era. The fuel temperature profiles, fuel and cladding deformation profiles, and radial temperature distribution at end of life (EOL) were evaluated by fuel performance analytical code CEDAR developed in JAEA to investigate the irradiation behavior of annular MOX fuel pins with (U,Pu) oxide fuel and Am bearing oxide fuel under a high burnup condition. Also, the profiles of pressure on the cladding inner surface and the cladding deformation after irradiation were evaluated.