Thierry Wiss

Profile Information
Name
Dr Thierry Wiss
Institution
European Commission
Position
Senior expert
Affiliation
JRC Karlsruhe
h-Index
33
ORCID
0000-0001-9725-1866
Biography

Dr. Thierry Wiss is Senior Scientist at the European Commission, Joint Research Centre. He graduated from the University of Paris XI in 1992, he obtained his PhD degree in radiochemistry from the University of Paris XI in 1997. He was recruited in the European Commission's Joint Research Centre (Karlsruhe, Germany) as scientific staff member in 1997 where he is Scientific Group Leader of the group "microanalyses" in the Nuclear Safety Fuel Unit. He is involved in radiation damage studies and in microstructural analyses of nuclear materials (mainly using electron microscopy). His activities are also related to the ageing of spent nuclear fuel and of waste matrices and more particularly on the effects of rare gas formation and defect interaction in nuclear materials.

He currently is reviewer for scientific journals, chairman in many international conferences, and participates to several scientific evaluation committees.

Expertise
Nuclear Fuel, Radiation Damage, Waste Disposal
NSUF Articles:
DOE Awards 33 Rapid Turnaround Experiment Research Proposals - Projects total approximately $1.2 million These projects will continue to advance the understanding of irradiation effects in nuclear fuels and materials in support of the mission of the DOE Office of Nuclear Energy. Monday, June 18, 2018 - Calls and Awards
Additional Publications:
"Cesium and iodine speciation in irradiated UO2 fuel" J.N. Zappey, O. Beneš, M. Cologna, T. Wiss, R.J.M. Konings, J.-Y. Colle, [2025] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2025.155715
"SUPERFACT: A Model Fuel for Studying the Evolution of the Microstructure of Spent Nuclear Fuel during Storage/Disposal" Oliver Dieste, Emanuele De Bona, Alessandro Benedetti, Vincenzo Rondinella, Rudy Konings, Thierry Wiss, [2021] Materials · DOI: 10.3390/ma14216538

The transmutation of minor actinides (in particular, Np and Am), which are among the main contributors to spent fuel α-radiotoxicity, was studied in the SUPERFACT irradiation. Several types of transmutation UO2-based fuels were produced, differing by their minor actinide content (241Am, 237Np, Pu), and irradiated in the Phénix fast reactor. Due to the high content in rather short-lived alpha-decaying actinides, both the archive, but also the irradiated fuels, cumulated an alpha dose during a laboratory time scale, which is comparable to that of standard LWR fuels during centuries/millenaries of storage. Transmission Electron Microscopy was performed to assess the evolution of the microstructure of the SUPERFACT archive and irradiated fuel. This was compared to conventional irradiated spent fuel (i.e., after years of storage) and to other 238Pu-doped UO2 for which the equivalent storage time would span over centuries. It could be shown that the microstructure of these fluorites does not degrade significantly from low to very high alpha-damage doses, and that helium bubbles precipitate.

"Radiation effects in alpha-doped UO2" A. Benedetti, O. Dieste, D. Staicu, T. Wiss, R.J.M. Konings, E. De Bona, [2020] Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms · DOI: 10.1016/j.nimb.2020.01.024
"Probing the local structure of nanoscale actinide oxides: a comparison between PuO2 and ThO2 nanoparticles rules out PuO2+x hypothesis" Matthieu Virot, Thomas Dumas, Adel Mesbah, Elodie Dalodière, Oliver Dieste Blanco, Thierry Wiss, Xavier Le Goff, Michael Odorico, Damien Prieur, André Rossberg, Laurent Venault, Nicolas Dacheux, Philippe Moisy, Sergey I. Nikitenko, Laura Bonato, [2020] Nanoscale Advances · DOI: 10.1039/c9na00662a

XRD, EXAFS and HR-TEM study reveals a strong correlation between AnO2 (An = Th and Pu) nanoparticle size and An(iv) local structure.

"TEM analysis of irradiation-induced interaction layers in coated UMo/X/Al trilayer systems (X= Ti, Nb, Zr, and Mo)" T. Wiss, S.-H. Park, O. Dieste-Blanco, W. Petry, H.-Y. Chiang, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2017.12.015
Source: ORCID/CrossRef using DOI