The maximum operating characteristics that can be achieved with the use of UO/sub 2/ as a reactor fuel are being investigated. Fuel assemblies are being fabricated for measurement of fission gas pressure in UO/sub 2/-filled fuel rods. A pressurized-water loop in GETR is being designed. A heat transfer burnout study is in progress to establish the upper limit of heat flux for studies of central melting in a fuel rod and fuel-cladding interactions. (M.C.G.
Activities in a project aimed at the improvement of fuel elements for high flux test reactors are re...
Thermal-conductivity measurements are in progress on an unirradiated, unclad, natural U specimen. Da...
Advanced Water Reactor Program. The second fuel loading for the EBWR is planned as ThO/sub 2/--UO/su...
The current PWR plant and core parameters are listed. Resign requirements are briefly summarized for...
The evolution of fission products from UO/sub 2/ during irradiation at high temperatures is of prima...
Since 1993, the Institute for Transuranium Elements and Framatome APN GmbH have been co-operating in...
BS>The thermal characteristics of various reactors fueled with uranium dioxide fuel pellets are l...
Abbreviated press feed preparations of UO/sub 2/ powder appear suitable for the automatic pressing o...
Advanced Fuel Power-Limit Test. Fabrication of the 50 basic fuel assemblies has been completed. The ...
Characterization and sintering results indicate significant differences between UO/sub 2/--35 wt% Pu...
Progress in the design, development, and construction of PWR power plant systems and components and ...
Work directed toward developing a stainless steel clad UO/sub 2/ fuel element is reported. Methods a...
Estimates indicate that, within the D/sub 2/O-moderated natural-uranium- fuel reactor category, the ...
During this reporting period, particular effort was of aced on powder blending and pellet sintering ...
A series of critical experiments were completed from 1962–1965 at Oak Ridge National Laboratory’s (O...
Activities in a project aimed at the improvement of fuel elements for high flux test reactors are re...
Thermal-conductivity measurements are in progress on an unirradiated, unclad, natural U specimen. Da...
Advanced Water Reactor Program. The second fuel loading for the EBWR is planned as ThO/sub 2/--UO/su...
The current PWR plant and core parameters are listed. Resign requirements are briefly summarized for...
The evolution of fission products from UO/sub 2/ during irradiation at high temperatures is of prima...
Since 1993, the Institute for Transuranium Elements and Framatome APN GmbH have been co-operating in...
BS>The thermal characteristics of various reactors fueled with uranium dioxide fuel pellets are l...
Abbreviated press feed preparations of UO/sub 2/ powder appear suitable for the automatic pressing o...
Advanced Fuel Power-Limit Test. Fabrication of the 50 basic fuel assemblies has been completed. The ...
Characterization and sintering results indicate significant differences between UO/sub 2/--35 wt% Pu...
Progress in the design, development, and construction of PWR power plant systems and components and ...
Work directed toward developing a stainless steel clad UO/sub 2/ fuel element is reported. Methods a...
Estimates indicate that, within the D/sub 2/O-moderated natural-uranium- fuel reactor category, the ...
During this reporting period, particular effort was of aced on powder blending and pellet sintering ...
A series of critical experiments were completed from 1962–1965 at Oak Ridge National Laboratory’s (O...
Activities in a project aimed at the improvement of fuel elements for high flux test reactors are re...
Thermal-conductivity measurements are in progress on an unirradiated, unclad, natural U specimen. Da...
Advanced Water Reactor Program. The second fuel loading for the EBWR is planned as ThO/sub 2/--UO/su...