Discover Uranium Dioxide

Laboratory continuous furnace for sintering of UO₂ pellets

Test E3 on high-energy transient meltdown of irradiated U0

Quality assurance and control in the manufacture of metal-clad UO₂ reactor fuels

In-pile determination of the thermal conductivity of UO₂ in the range 500-2500 degrees centigrade

Studies in sintering of UO₂: relation between electrical conductivity and microstructure of sintered UO₂

Test E3 on high-energy transient meltdown of irradiated U0b2s in a TREAT Mark-II loop

Thermal conductivity and emittance of solid UO₂

A study of the temperature distribution in UO₂ reactor fuel elements

Pilot plant for manufacture of UO₂ pellets

Kinetics of release of xenon from sintered (ThO₂-O.1% UO₂) pellets

Emissivity data for uranium dioxide

Study on chemical reactions between uranium dioxide, the most abundant fission products, water and sodium

Test E3 on high-energy transient meltdown of irradiated U0b2s in a TREAT Mark-II loop

The fabrication of U233/ aluminium fuel plates for sub-critical assembly - a second report

Test E3 on high-energy transient meltdown of irradiated U0

In-core study of fuel/clad interaction and fuel centre temperature

Experimental determination of the U-238 excess resonance neutron capture integrals of three clustered fuel elements

Tekhnologii͡a︡ poluchenii͡a︡ poroshkov keramicheskoĭ dvuokisi urana