U-Mo dispersions in Al-alloy matrix and monolithic fuels encased in Al-alloy are under development to fulfill the requirements for research and test reactors to use low-enriched molybdenum stabilized uranium alloy fuels. Significant interaction takes place between the U-Mo fuel and Al during manufacturing and in-reactor irradiation. The interaction products are Al-rich phases with physical and thermal characteristics that adversely affect fuel performance and result in premature failure. Detailed analysis of the interdiffusion and microstructural development of this system was carried through diffusion couples consisting of U-7 wt pct Mo, U-10 wt pct Mo and U-12 wt pct Mo in contact with pure Al, Al-2 wt pct Si, and Al-5 wt pct Si, annealed...
Interdiffusion and microstructural development in the U-Mo-Al system was examined using solid-tosoli...
U-Mo has thus far proven to be one of the most feasible metallic fuel alloys for use in research and...
This study examined the growth kinetics of intermetallic phases that develop in solid-to-solid diffu...
International audienceWithin the framework of the development of low enriched nuclear fuels for rese...
International audienceSi addition to Al is considered as a promising route to reduce (U,Mo)-Al inter...
U-Mo dispersion and monolithic fuels are being developed to fulfill the requirements for research re...
International audienceU(Mo)/Al(Si) diffusion couples are studied to provide a better understanding o...
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...
The U.S. Material Management and Minimization Reactor Conversion Program is developing low enrichmen...
U-Mo alloys are being developed as low enrichment uranium fuels under the Reduced Enrichment for Res...
The Reduced Enrichment for Research and Test Reactors (RERTR) program has been developing low enrich...
U-Mo alloys are being developed as low enrichment uranium fuels under the Reduced Enrichment for Res...
Interdiffusion and microstructural development in the U-Mo-Al system was examined using solid-tosoli...
U-Mo has thus far proven to be one of the most feasible metallic fuel alloys for use in research and...
This study examined the growth kinetics of intermetallic phases that develop in solid-to-solid diffu...
International audienceWithin the framework of the development of low enriched nuclear fuels for rese...
International audienceSi addition to Al is considered as a promising route to reduce (U,Mo)-Al inter...
U-Mo dispersion and monolithic fuels are being developed to fulfill the requirements for research re...
International audienceU(Mo)/Al(Si) diffusion couples are studied to provide a better understanding o...
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...
The U.S. Material Management and Minimization Reactor Conversion Program is developing low enrichmen...
U-Mo alloys are being developed as low enrichment uranium fuels under the Reduced Enrichment for Res...
The Reduced Enrichment for Research and Test Reactors (RERTR) program has been developing low enrich...
U-Mo alloys are being developed as low enrichment uranium fuels under the Reduced Enrichment for Res...
Interdiffusion and microstructural development in the U-Mo-Al system was examined using solid-tosoli...
U-Mo has thus far proven to be one of the most feasible metallic fuel alloys for use in research and...
This study examined the growth kinetics of intermetallic phases that develop in solid-to-solid diffu...