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Thermal Conductivity Measurement of Zr-ZrO<sub>2</sub> Simulated Inert Matrix Nuclear Fuel Pellet

¹ LWR Fuel Technology Division, Korea Atomic Energy Research Institute, Daejeon, South Korea
² LWR Fuel Technology Division, Korea Atomic Energy Research Institute, Daejeon, South Korea
³ LWR Fuel Technology Division, Korea Atomic Energy Research Institute, Daejeon, South Korea
⁴ LWR Fuel Technology Division, Korea Atomic Energy Research Institute, Daejeon, South Korea
⁵ LWR Fuel Technology Division, Korea Atomic Energy Research Institute, Daejeon, South Korea
⁶ LWR Fuel Technology Division, Korea Atomic Energy Research Institute, Daejeon, South Korea

World Journal of Nuclear Science and Technology·Volume 03 (2013)·Pages 46–50·Published 30 April 2013·DOI10.4236/wjnst.2013.32008

Abstract

For an evaluation of a thermal conductivity of Zr + 30 vol% ZrO 2 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.

KeywordsInert Matrix Nuclear FuelDispersion FuelThermal ConductivityThermal ExpansionSpecific Heat

IAEA-TECDOC-1516, “Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors,” IAEA, VIENNA, 2006.
G. Ledergerber, C. Degueldre, P. Heimgartner, M. A. Pouchon and U. Kasemeyer, “Inert Matrix Fuel for the Utilization of Plutonium,” Progress in Nuclear Energy, Vol. 38, No. 3, 2001, pp. 301-308. doi:10.1016/S0149-1970(00)00122-0
R. Fielding, M. Meyer, J. Jue and J. Gan, “Gas-Cooled Fast Reactor Fuel Fabrication,” Journal of Nuclear Materials, Vol. 371, No. 1, 2007, pp. 243-249. doi:10.1016/j.jnucmat.2007.05.011
M. K. Meyer, R. Fielding and J. Gan, “Fuel Development for Gas-Cooled Fast Reactors,” Journal of Nuclear Materials, Vol. 371, No. 1-3, 2007, pp. 281-287. doi:10.1016/j.jnucmat.2007.05.013
D. E. Burkes, R. S. Fielding, D. L. Porter, M. K. Meyer and B. J. Makenas, “A US Perspective on Fast Reactor Fuel Fabrication Technology and Experience. Part II: Ceramic Fuels,” Journal of Nuclear Materials, Vol. 393, No. 1, 2009, pp. 1-11. doi:10.1016/j.jnucmat.2009.04.023
M. Burghartz, H. J. Matzke, C. Léger, G. Vambenepe and M. Rome, “Inert Matrices for the Transmutation of actinides: Fabrication, Thermal Properties and Radiation Stability of Ceramic Materials,” Journal of Alloy and Compound, Vol. 271-273, 1998, pp. 544-548. doi:10.1016/S0925-8388(98)00149-2
H. Kleykamp, “Selection of Materials as Diluents for Burning of Plutonium Fuels in Nuclear Reactors,” Journal of Nuclear Materials, Vol. 275, No. 1, 1999, pp. 1-11. doi:10.1016/S0022-3115(99)00144-0
M. A. Pouchoun, C. Degueldre and P. Tissot, “Determination of the Thermal Conductivity in Zirconia Based Inert Matrix Nuclear Fuel by Oscillating Differential Scanning Calorimetry and Laser Flash,” Thermochimica Acta, Vol. 323, No. 1-2, 1998, pp. 109-121. doi:10.1016/S0040-6031(98)00504-8
Y.-W. Lee, H. S. Kim, S. H. Kim, C. Y. Joung, S. H. Na, G. Ledergerber, P. Heimgartner, M. Pouchon and M. Burghartz, “Preparation of Simulated Inert Matrix Fuel with Different Powders by Dry Milling Method,” Journal of Nuclear Materials, Vol. 274, No. 1-2, 1999, pp. 7-14. doi:10.1016/S0022-3115(99)00094-X
K. S. Kumar, T. Mathews and N. P. Bhat, “Study on Thermal Decomposition and Sintering Behaviour of Internally Gelated Simulated Inert Matrix Fuel,” Thermochimica Acta, Vol. 427, No. 1-2, 2005, pp. 27-30. doi:10.1016/j.tca.2004.08.008
S. Baldi, J. Porta, Y. Peneleau, S. Pelloni, J.-M. Paratte and R. Chawla, “Importance of Zirconium Cross Sections in Calculating Reactivity Effects for Inert Matrix Fuels,” Progress in Nuclear Energy, Vol. 38, No. 3-4, 2001, pp. 351-354. doi:10.1016/S0149-1970(00)00133-5

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Thermal Conductivity Measurement of Zr-ZrO<sub>2</sub> Simulated Inert Matrix Nuclear Fuel Pellet

Abstract

References (24)