Thermal Conductivity Measurement of Zr-ZrO₂ Simulated Inert Matrix Nuclear Fuel Pellet

Dong-Joo Kim, Young Woo Rhee, Jong Hun Kim, Jang Soo Oh, Keon Sik Kim, Jae Ho Yang

LWR Fuel Technology Division, Korea Atomic Energy Research Institute, Daejeon, South Korea.

DOI: 10.4236/wjnst.2013.32008                

Abstract

For an evaluation of a thermal conductivity of Zr + 30 vol% ZrO₂ simulated inert matrix nuclear fuel pellet, a simulated fuel pellet was fabricated using a hot-pressing method at 800°C in a vacuum and at a 20 MPa load. And several thermophysical properties of the simulated inert matrix fuel pellet were measured and calculated. The thermal diffusivity and linear thermal expansion as a function of temperature of the simulated fuel pellet were measured using a laser flash method and a dilatometry, respectively. Finally, based on the experimental data, the thermal conductivity of the simulated inert matrix fuel pellet was calculated and evaluated.

Keywords

Inert Matrix Nuclear Fuel; Dispersion Fuel; Thermal Conductivity; Thermal Expansion; Specific Heat

Conflicts of Interest

The authors declare no conflicts of interest.

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