International audienceWithin the framework of the development of low enriched nuclear fuels for research reactors, U-Mo/Al is the most promising option that has however to be optimised. Indeed at the U-Mo/Al interfaces between U-Mo particles and the Al matrix, an interaction layer grows under irradiation inducing an unacceptable fuel swelling. Adding silicon in limited content into the Al matrix has clearly improved the in-pile fuel behaviour. This breakthrough is attributed to an U-Mo/Al-Si protective layer around U-Mo particles appeared during fuel manufacturing. In this work, the evolution of the microstructure and composition of this protective layer with increasing Si concentrations in the Al matrix has been investigated. Conclusions a...
RERTR U-Mo dispersion fuel plates are being developed for application in research reactors throughou...
International audienceIn the framework of the development of a low 235U enriched nuclear fuel for ma...
During fabrication of U-7Mo dispersion fuels, exposure to relatively high temperatures affects the f...
International audienceWithin the framework of the development of low enriched nuclear fuels for rese...
U-Mo dispersions in Al-alloy matrix and monolithic fuels encased in Al-alloy are under development t...
High-density uranium (U) alloys with an increased concentration of U are being examined for the deve...
High-density uranium (U) alloys with an increased concentration of U are being examined for the deve...
International audienceU(Mo)/Al(Si) diffusion couples are studied to provide a better understanding o...
Published data concerning the interaction layer (IL) formed between U-xMo fuel alloy and aluminum (A...
International audienceSi addition to Al is considered as a promising route to reduce (U,Mo)-Al inter...
Interaction layer growth between U-Mo alloy fuel particles and Al in a dispersion fuel is a concern ...
Interaction layer growth between U-Mo alloy fuel particles and Al in a dispersion fuel is a concern ...
<p></p><p>ABSTRACT Fuel elements based on U3Si2 particles dispersed in a pure Al matrix (known as di...
RERTR U-Mo dispersion fuel plates are being developed for application in research reactors throughou...
International audienceIn the framework of the development of a low 235U enriched nuclear fuel for ma...
During fabrication of U-7Mo dispersion fuels, exposure to relatively high temperatures affects the f...
International audienceWithin the framework of the development of low enriched nuclear fuels for rese...
U-Mo dispersions in Al-alloy matrix and monolithic fuels encased in Al-alloy are under development t...
High-density uranium (U) alloys with an increased concentration of U are being examined for the deve...
High-density uranium (U) alloys with an increased concentration of U are being examined for the deve...
International audienceU(Mo)/Al(Si) diffusion couples are studied to provide a better understanding o...
Published data concerning the interaction layer (IL) formed between U-xMo fuel alloy and aluminum (A...
International audienceSi addition to Al is considered as a promising route to reduce (U,Mo)-Al inter...
Interaction layer growth between U-Mo alloy fuel particles and Al in a dispersion fuel is a concern ...
Interaction layer growth between U-Mo alloy fuel particles and Al in a dispersion fuel is a concern ...
<p></p><p>ABSTRACT Fuel elements based on U3Si2 particles dispersed in a pure Al matrix (known as di...
RERTR U-Mo dispersion fuel plates are being developed for application in research reactors throughou...
International audienceIn the framework of the development of a low 235U enriched nuclear fuel for ma...
During fabrication of U-7Mo dispersion fuels, exposure to relatively high temperatures affects the f...