Author

T. Wiss

Observed names: T Wiss, T.A.G Wiss, T.A.G. Wiss, Thierry Wiss, Wiss, T., Wiss, Thierry

Observed institutions: Karlsruhe Institute of Technology, European Commission, Joint Research Center, Joint Research Centre, Joint Research Centre, Directorate-General Joint Research Centre, Joint Research Centre, Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas, Istanbul Technical University, IT University of Copenhagen

ORCID: 0000-0001-9725-1866

Observed ORCID: 0000-0001-9725-1866

OpenAlex ID: A5004233644

The high burn-up structure in nuclear fuel

2010 · Vincenzo V. Rondinella, Thierry Wiss · Materials Today · 328

Transmission electron microscopy observation on irradiation-induced microstructural evolution in high burn-up UO2 disk fuel

2002 · T. Sonoda, M. Kinoshita, et al. · Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms · 137

Materials research on inert matrices: a screening study

1999 · Hj Matzke, V.V Rondinella, et al. · Journal of Nuclear Materials · 124

Predicting material release during a nuclear reactor accident

2015 · Rudy J. M. Konings, Thierry Wiss, et al. · Nature Materials · 115

Radiation damage in UO2 by swift heavy ions

1997 · T. Wiss, Hj. Matzke, et al. · Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms · 114

Zirconate pyrochlore as a transmutation target: thermal behaviour and radiation resistance against fission fragment impact

2003 · S. Lutique, D. Staicu, et al. · Journal of Nuclear Materials · 102

Swift heavy ion and fission damage effects in UO2

2000 · Hj. Matzke, P.G. Lucuta, et al. · Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms · 100

The thermal conductivity of Nd2Zr2O7 pyrochlore and the thermal behaviour of pyrochlore-based inert matrix fuel

2003 · S. Lutique, R.J.M. Konings, et al. · Journal of Alloys and Compounds · 97

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

2008 · J.-P. Hiernaut, T. Wiss, et al. · Journal of Nuclear Materials · 96

Evolution of spent nuclear fuel in dry storage conditions for millennia and beyond

2014 · Thierry Wiss, Jean-Pol Hiernaut, et al. · Journal of Nuclear Materials · 83

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Low temperature decomposition of U(IV) and Th(IV) oxalates to nanograined oxide powders

2015 · Vaclav Tyrpekl, Jean-Francois Vigier, et al. · Journal of Nuclear Materials · 81

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Impact of auto-irradiation on the thermophysical properties of oxide nuclear reactor fuels

2009 · D. Staicu, T. Wiss, et al. · Journal of Nuclear Materials · 81