[2F11-15] Next Generation Fuel, Accident Tolerant Fuel

[2F12] MOX fuel technologies for next-generation nuclear reactors

(2) Study of thermal conductivity and irradiation behavior for MOX fuel

*Takumi Oki¹, Masato Kato¹, Yoshihisa Ikusawa¹, Shun Hirooka¹ (1. JAEA)

Keywords: Fast reactor, Mixed oxide, Thermal conductivity, Irradiation behavior

The thermal conductivity in high temperature range considering Bredick transition was studied based on the irradiation test data, and the irradiation behavior was evaluated using our analytical code. The thermal conductivity considering Bredick transition increases from around 1500 K and peaks around 2200 K. By evaluating the irradiation behavior using this thermal conductivity, it was confirmed that the fuel center temperature from low temperature range to just below the melting point reproduced the measured value.