W. Goll

Matrix swelling rate and cavity volume balance of UO2 fuels at high burn-up

J. Spino, J. Rest, W. Goll et al. · Journal of Nuclear Materials · 2005 · 102 citations

Materials Science, Chemical Engineering, Engineering +8

Fission product release and microstructure changes during laboratory annealing of a very high burn-up fuel specimen

J.-P. Hiernaut, T. Wiss, Jean‐Yves Colle et al. · Journal of Nuclear Materials · 2008 · 85 citations

Materials Science, Nuclear Ceramic, Microstructure Changes +10

On the thermal conductivity of UO2 nuclear fuel at a high burn-up of around 100MWd/kgHM

C.T. Walker, D. Staicu, M. Sheindlin et al. · Journal of Nuclear Materials · 2006 · 80 citations

Materials Science, Nuclear Fuel Burnup, Engineering +11

SIMS analysis of an UO2 fuel irradiated at low temperature to 65MWd/kgHM

C.T. Walker, S. Brémier, S. Portier et al. · Journal of Nuclear Materials · 2009 · 56 citations

Nuclear Ceramic, Chemical Engineering, Engineering +9

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 · 56 citations

Chemical Engineering, Nuclear Fuel Burnup, Engineering +10