## Abstract

An inert matrix fuel material based on yttria-stabilized cubic zirconia: Er_{x}Y_{y}Pu_{z}Zr_{1-x-y-z}O_{2-(x + y)/2} (x + y = 0.15, z: [0.05-0.15]) was proposed for burning excess plutonium in light water reactors. The studied inert matrix fuel is made of cubic stabilized zirconia. The limited number of experimental thermal conductivity data justifies this formal and intensive study. Approaches derived from Klemens theory were revisited and the derived conductivity model applied for zirconia, accounting the effects of phononic scattering centers. The hyperbolic thermal conductivity trend with temperature known for pure zirconia, is reduced by isotopes, impurities, dopants and oxygen vacancies, which act as scattering centers and contribute to conductivity reduction to a flat plot with temperature for stabilized zirconia. It is experimentally observed that the thermal conductivity derived from laser flash measurements for Er_{x}Y_{y}M_{z}Zr_{1-x-y-z}O_{2-(x + y)/2} (with M = Ce or Pu, z = 0 or ∼ 0.1 and x + y = 0.15) is rather constant as a function of temperature in the range 300-1000 K. The thermal conductivity was observed to depend on the concentration of dopants such as YO_{1.5} and/or ErO_{1.5}, CeO_{2} (analogous of PuO_{2}) or PuO_{2}. The bulk material conductivity of Er_{0.05}Y_{0.10}Pu_{0.10}Zr_{0.75}O_{1.925 } is about 2 Wm^{-1}K^{-1}. In this study, the thermal conductivity data of both monoclinic and stabilized cubic zirconia based IMF are tested with the model approach in order to understand the experimental data in a semi-quantitative way.

Original language | English |
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Pages (from-to) | 6-14 |

Number of pages | 9 |

Journal | Journal of Nuclear Materials |

Volume | 319 |

DOIs | |

Publication status | Published - Jun 1 2003 |

Event | Proceedings of the 8th Inert Matrix Fuel Workshop - Tokai, Japan Duration: Oct 16 2002 → Oct 18 2002 |

## All Science Journal Classification (ASJC) codes

- Nuclear and High Energy Physics
- Materials Science(all)
- Nuclear Energy and Engineering