Inert matrix fuel for the utilisation of plutonium

Lattice Parameters, Ionic Conductivities, and Solubility Limits in Fluorite‐Structure MO ₂ Oxide [M = Hf ⁴⁺ , Zr ⁴⁺ , Ce ⁴⁺ , Th ⁴⁺ , U ⁴⁺ ] Solid Solutions

Dae‐Joon Kim · Journal of the American Ceramic Society · 1989 · 630 citations

Natural Sciences, Chemistry, Materials Science +17

The diffusion coefficients of gaseous and volatile species during the irradiation of uranium dioxide

J.A. Turnbull, C.A. Friskney, J.R. Findlay et al. · Journal of Nuclear Materials · 1982 · 296 citations

Natural Sciences, Nuclear Engineering, Physics +16

<b><i>Ab initio</i></b>study of structural and electronic properties of yttria-stabilized cubic zirconia

G. Stapper, Marco Bernasconi, N. Nicoloso et al. · Physical review. B, Condensed matter · 1999 · 295 citations

Natural Sciences, Materials Science, Physics +17

Plutonium Incineration in LWR's by a Once-Through Cycle with a Rock-Like Fuel

C. Degueldre, U. Kasemeyer, Fabio Botta et al. · MRS Proceedings · 1995 · 81 citations

Engineering, Earth Sciences, Nuclear Engineering +16

Preparation of simulated inert matrix fuel with different powders by dry milling method

Y.-W Lee, H.S Kim, S.H Kim et al. · Journal of Nuclear Materials · 1999 · 73 citations

Natural Sciences, Materials Engineering, Materials Science +15