Thermophysical Properties of MOX and UO2 Fuels Including the Effects of Irradiation

[摘要] Available open literature on thermophysical properties of both MOX and UO{sub 2} fuels has been reviewed, and the best set of thermal properties has been selected. The properties reviewed are solidus and liquidus temperatures of the uranium-plutonium dioxide system (melting temperature), thermal expansion, density, heat of fusion, enthalpy, specific heat, and thermal conductivity. Only fuel properties are studied in this report. The selected properties are used in thermal-hydraulic codes to study design basis accidents. The majority of the properties presented are for solid fuel.

[发布日期] 2001-01-11 [发布机构] Oak Ridge National Laboratory

[关键词] Specific Heat;Uranium Dioxide;Thermal Conductivity;Density;Thermal Expansion