Explore Books on
uranium dioxide

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

By Panel on Quality Assurance and Control in Nuclear Fuel Manufacture Vienna 1974.

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

By Jan-Åke Gyllander

A study of the temperature distribution in UO₂ reactor fuel elements

By I. Devold

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

By J. Bardsley

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

By M. D. Karkhanavala

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

By W. Ch Buck

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

By Surumpudy Venkata Krishna Rao

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

By Norbert Henzel

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

By Gudolf Kjærheim

Laboratory continuous furnace for sintering of UO₂ pellets

By O. Toft Sørensen

Pilot plant for manufacture of UO₂ pellets

By O. Toft Sørensen

Thermal conductivity and emittance of solid UO₂

By R. Brandt

Emissivity data for uranium dioxide

By Thomas Tucker Claudson

Test E3 on high-energy transient meltdown of irradiated U0

By Argonne National Laboratory. Reactor Analysis and Safety Division

Test E3 on high-energy transient meltdown of irradiated U0

By Argonne National Laboratory. Reactor Analysis and Safety Division

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

By Argonne National Laboratory. Reactor Analysis and Safety Division

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

By Argonne National Laboratory. Reactor Analysis and Safety Division

Tekhnologii͡a︡ poluchenii͡a︡ poroshkov keramicheskoĭ dvuokisi urana

By A. A. Maĭorov