T. Wiss - Concepedia

Author

T. Wiss

Joint Research Centre ORCID

Also Known As

T Wiss, T. Wiss, T.A.G Wiss, T.A.G. Wiss, Thierry Wiss, Wiss, T., Wiss, Thierry

151

Publications

3.1K

Citations

H-Index

Concepts

All Affiliations

Joint Research Centre Commissariat à l'Énergie Atomique et aux Énergies Alternatives Centre National de la Recherche Scientifique Direction des Energies FZI Research Center for Information Technology

About

T. Wiss is an author at Joint Research Centre specializing in engineering, materials science, and chemistry.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	27	51	2.3K
2	Chemistry	20	29	1.4K
3	Chemical Engineering	16	21	833
4	Natural Sciences	13	14	935
5	Applied Physics	9	9	373

T. Wiss

Publications

2.8K

Citations

H-Index

Page 1

	Year	Citations
The high burn-up structure in nuclear fuel V.V. Rondinella, T. Wiss Materials Today EngineeringNuclear PhysicsReactor DesignNuclear Reactor DesignChemistry	2010	310
Materials research on inert matrices: a screening study Hj. Matzke, V.V. Rondinella, T. Wiss Journal of Nuclear Materials Materials ScienceEngineeringMechanical BehaviorMechanicsMaterial System	1999	126
Transmission electron microscopy observation on irradiation-induced microstructural evolution in high burn-up UO2 disk fuel T. Sonoda, M. Kinoshita, I. L. F. Ray, Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms Materials ScienceEngineeringOxide ElectronicsApplied PhysicsMicroanalysis	2002	122
Radiation damage in UO2 by swift heavy ions T. Wiss, Hj. Matzke, C. Trautmann, Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms Heavy Ion PhysicNuclear PhysicsPhysicsNatural SciencesAtomic Physics	1997	111
Predicting material release during a nuclear reactor accident R.J.M. Konings, T. Wiss, O. Beneš Nature Materials EngineeringNuclear EngineeringNuclear SafetyReactor SafetyNuclear Materials	2015	108
Zirconate pyrochlore as a transmutation target: thermal behaviour and radiation resistance against fission fragment impact S. Lutique, D. Staicu, R.J.M. Konings, Journal of Nuclear Materials Materials ScienceTransmutation TargetChemical EngineeringFission Fragment ImpactEngineering	2003	103
The thermal conductivity of Nd2Zr2O7 pyrochlore and the thermal behaviour of pyrochlore-based inert matrix fuel S. Lutique, R.J.M. Konings, V.V. Rondinella, Journal of Alloys and Compounds Materials ScienceChemical EngineeringEngineeringThermal BehaviourThermal Transport	2003	98
Swift heavy ion and fission damage effects in UO2 Hj. Matzke, P.G. Lucuta, T. Wiss Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms EngineeringNuclear PhysicsNuclear FissionNatural SciencesAtomic Physics	2000	96
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, Journal of Nuclear Materials Materials ScienceNuclear CeramicMicrostructure ChangesEngineeringNuclear Fuel Burnup	2008	85
Evolution of spent nuclear fuel in dry storage conditions for millennia and beyond T. Wiss, J.-P. Hiernaut, D. Roudil, Journal of Nuclear Materials Nuclear Waste ManagementEngineeringRadioactive ContaminationRadioactive WasteDry Storage Conditions	2014	78

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