International audienceGraphite and magnesium alloys wastes were generated during the reprocessing phase of spent fuel assemblies of the former nuclear reactors in France. Conditioning of these low to intermediate level wastes in cementitious materials is being addressed here. The study is held in the framework of a PhD thesis aiming to develop a numerical model able to predict the generation of stresses in such waste packages during their lifetime.In fact, magnesium is one of the most reactive metals with a standard normal potential of -2.37mV/SHE [1]. Once embedded in a hydraulic binder with alkaline pH and high internal humidity, oxidation reactions occur. The subsequent formation of corrosion products around the alloy may result in tensi...
The chemistry and corrosion mechanisms associated with reduced sulfur compounds such as calcium sulf...
Introduction The Belgian Reactor 1 (BR1) fuel is composed of natural unalloyed metallic uranium, coa...
Magnesium alloys are well known for their high specific strength. There is growing interest in the a...
International audienceGraphite and magnesium alloys wastes were generated during the reprocessing ph...
International audienceThe reprocessing of spent fuel from the French UNGG (Graphite Gas Natural Uran...
International audienceMagnesium alloys and graphite from spent nuclear fuel have been stored togethe...
International audiencePortland cement is extensively used for the conditioning of radioactive waste....
International audienceThe reprocessing of spent fuels from UNGG (Uranium Natural Graphite Gas) nucle...
International audienceThe reprocessing of spent fuel designed for natural uranium – graphite – gas r...
The reprocessing of spent fuels from UNGG (Uranium Natural Graphite Gas) nuclear reactors in France ...
National audienceThe operation of the first generation of nuclear reactors in France has generated m...
The present study concerns the influence of cementitious binder on electrochemical treatment of stee...
A novel low pH magnesium silicate hydrate cement system for encapsulating nuclear industry wastes ha...
This thesis deals with the characterization of electrochemical corrosion properties of magnesium all...
The chemistry and corrosion mechanisms associated with reduced sulfur compounds such as calcium sulf...
Introduction The Belgian Reactor 1 (BR1) fuel is composed of natural unalloyed metallic uranium, coa...
Magnesium alloys are well known for their high specific strength. There is growing interest in the a...
International audienceGraphite and magnesium alloys wastes were generated during the reprocessing ph...
International audienceThe reprocessing of spent fuel from the French UNGG (Graphite Gas Natural Uran...
International audienceMagnesium alloys and graphite from spent nuclear fuel have been stored togethe...
International audiencePortland cement is extensively used for the conditioning of radioactive waste....
International audienceThe reprocessing of spent fuels from UNGG (Uranium Natural Graphite Gas) nucle...
International audienceThe reprocessing of spent fuel designed for natural uranium – graphite – gas r...
The reprocessing of spent fuels from UNGG (Uranium Natural Graphite Gas) nuclear reactors in France ...
National audienceThe operation of the first generation of nuclear reactors in France has generated m...
The present study concerns the influence of cementitious binder on electrochemical treatment of stee...
A novel low pH magnesium silicate hydrate cement system for encapsulating nuclear industry wastes ha...
This thesis deals with the characterization of electrochemical corrosion properties of magnesium all...
The chemistry and corrosion mechanisms associated with reduced sulfur compounds such as calcium sulf...
Introduction The Belgian Reactor 1 (BR1) fuel is composed of natural unalloyed metallic uranium, coa...
Magnesium alloys are well known for their high specific strength. There is growing interest in the a...