Solid surface evolution model to predict uranium release from unirradiated UO2 and nuclear spent fuel dissolution under oxidizing conditions

Spent fuel corrosion and dissolution

R.S. Forsyth, L. Werme · Journal of Nuclear Materials · 1992 · 132 citations

Natural Sciences, Materials Engineering, Materials Science +12

The kinetics of dissolution of UO2 under reducing conditions and the influence of an oxidized surface layer (UO2+x): Application of a continuous flow-through reactor

Jordi Bruno, I. Casas, I. Puigdomènech · Geochimica et Cosmochimica Acta · 1991 · 123 citations

Natural Sciences, Chemical Engineering, Chemistry +14

Oxidation of uranium dioxide at 298 K studied by using x-ray photoelectron spectroscopy

G. C. Allen, P. M. Tucker, J. W. TYLER · The Journal of Physical Chemistry · 1982 · 111 citations

Natural Sciences, Chemistry, Analytical Chemistry +8

The corrosion of nuclear fuel (UO2) in oxygenated solutions

David W. Shoesmith, S. Sunder, M.G. Bailey et al. · Corrosion Science · 1989 · 81 citations

Natural Sciences, Materials Science, Nuclear Engineering +14

Oxidation of spent fuel in air at 175 to 195°C

R.E. Einziger, L. E. Thomas, H.C. Buchanan et al. · Journal of Nuclear Materials · 1992 · 55 citations

Engineering, Chemical Engineering, Chemistry +12