1. Steady- and transient-state analyses of fully ceramic microencapsulated fuel with randomly dispersed TRISO particles via two-temperature homogenized model—I: theory and method;Lee;Nucl. Eng. Technol.,2016
2. Comparison of Monte Carlo simulation models for randomly distributed particle fuels in VHTR Fuel Element;Yu;Trans. Am. Nucl. Soc.,2006
3. Theory Manual for the Rectangular Three-Dimensional Diffusion Nodal Code COREDAX-2 Version 1.5, KINS/HR-1356 Rev. 1, NURAPT-2015-02;Cho,2015
4. Thermal conductivity correlation for uranium nitride fuel between 10 and 1923 K;Ross;J. Nucl. Mater.,1988
5. Thermophysical Properties Database of Materials for Light Water Reactor and Heavy Water Reactors, IAEA-TECDOC-1496;IAEA,2006