Article citationsMore>>

A. Savchenko, I. Konovalov, S. Ershov, A. Laushkin, G. Kulakov, S. Maranchak, Y. Konovalov and E. Malamanova, “Zirconium Matrix Alloys for High Uranium Content Dispersion Type Fuel,” International Meeting on LWR Fuel Performance, Salamanca, 2006.

has been cited by the following article:

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

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

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

  JOURNAL NAME: World Journal of Nuclear Science and Technology, Vol.3 No.2, April 30, 2013

  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.