Experimental evidence of oxygen thermo-migration in PWR UO2 fuels during power ramps using in-situ oxido-reduction indicators

The chemical state of LWR high-power rods under irradiation

H. Kleykamp · Journal of Nuclear Materials · 1979 · 102 citations

Engineering, Materials Engineering, Materials Science +14

Oxygen redistribution in fast reactor oxide fuel

C. Sari, G. Schumacher · Journal of Nuclear Materials · 1976 · 86 citations

Engineering, Nuclear Engineering, Nuclear Fuel Cycle +7

On the solubility of chromium sesquioxide in uranium dioxide fuel

A. Leenaers, L. de Tollenaere, Ch. Delafoy et al. · Journal of Nuclear Materials · 2003 · 64 citations

Engineering, Chemistry, Nuclear Engineering +13

Thermodynamics of chromium in UO2 fuel: A solubility model

Ch. Riglet-Martial, P. Martín, D. Testemale et al. · Journal of Nuclear Materials · 2014 · 61 citations

Natural Sciences, Chemical Engineering, Chemistry +14

On the oxidation state of UO2 nuclear fuel at a burn-up of around 100MWd/kgHM

C.T. Walker, V.V. Rondinella, D. Papaioannou et al. · Journal of Nuclear Materials · 2005 · 57 citations

Engineering, Chemistry, Nuclear Engineering +14