2018 Annual Meeting

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 401-2 Nuclear Fuel and the Irradiation Behavior

[3D01-05] MOX Fuels for Fast Reactor

Wed. Mar 28, 2018 9:30 AM - 10:55 AM Room D (R1-212 -R1 Building)

Chair: Shuhei Miwa (JAEA)

10:00 AM - 10:15 AM

[3D03] Science-based Integrated Models for MOX Properties

(3)Heat capacity and thermal conductivity

*Masato Kato1, Kyoichi Morimoto1, Hiroki Nakamura1, Masahiko Machida1 (1. Japan Atomic Energy Agency)

Keywords:MOX, Physical Property, Heat capacity, Thermal conductivity

The model which evaluates the specific heat and a thermal conductivities of MOX fuels was derived using sound speeds, lattice parameter, thermal expansion and oxygen potential. The model named Science-based Integrated Models for MOX Properties (ScIM for MOXProp) can describe various physical property data as functions of temperature, Pu content, MA content and O/M ratio. The model will be applied to a fuel performance code seamlessly as parameters of fuel compositions.