论文信息 - A method for determining an effective porosity correction factor for thermal conductivity in fast reactor uranium–plutonium oxide fuel pellets - 字舞流文

A method for determining an effective porosity correction factor for thermal conductivity in fast reactor uranium–plutonium oxide fuel pellets

M. Inoue | I. Sato | K. Abe

[1] K. Bakker,et al. Determination of a porosity correction factor for the thermal conductivity of irradiated U02 fuel by means of the finite element method , 1995 .

[2] K. Yoshikawa,et al. Melting temperature and thermal conductivity of irradiated mixed oxide fuel , 1993 .

[3] Y. Philipponneau,et al. Thermal conductivity of (U, Pu)O2−x mixed oxide fuel , 1992 .

[4] John H. Harding,et al. A recommendation for the thermal conductivity of UO2 , 1989 .

[5] P. Nikolopoulos,et al. Conductivity bounds for porous nuclear fuels , 1983 .

[6] D. G. Martin. A re-appraisal of the thermal conductivity of UO2 and mixed (U, Pu) oxide fuels , 1982 .

[7] A. L. Loeb. Thermal Conductivity: VIII, A Theory of Thermal Conductivity of Porous Materials , 1954 .

[8] J. Fink. Enthalpy and heat capacity of the actinide oxides , 1982 .