The thermodynamic data for unirradiated dioxides in the U- ThPu-O system are briefly reviewed. Calculations of oxygen release during fission were made and were found to agree qualitatively with experimental measurements. Theories were developed for prediction of mass transport rates in oxide particles; these included control by either CO-- CO/sub 2/ diffusion, reactions such as disproportionation of carbon monoxide, or solid-state diffusion through the kernel. Methods were devised for the determination of the general type of rate- controlling mechanism from the quantitative analysis of inreactor and out-of- reactor experiments. Application of these methods to an in-pile experiment indicated that CO-- CO/sub 2/ diffusion did not control the ...
ABSTRACT For Very High Temperature Reactors (V-HTR), the study of the Uranium-Carbon-Oxygen system i...
The objective of the Fuel Cycle R&D Program, Advanced Fuels campaign is to provide the research ...
The emission of uranium and ruthenium oxides from overheated nuclear fuel is a complex phenomenon wh...
Literature values and estimated data for the thermodynamics of the actinide oxides and fission produ...
Metal oxides added to UO2 to improve material performance during irradiation, or as burnable absorb...
The evolution of fission products from UO/sub 2/ during irradiation at high temperatures is of prima...
An analytical approach is proposed which allows the bunnup (by fission) of uranium required to cause...
Supported by results of calculations performed with two analytical tools (MFPR, which takes account ...
International audienceThermo-Desorption Spectrometry (TDS) was employed to study the release of fiss...
A series of hot-cell tests was conducted with UO{sub 2} that had been irradiated to an average of 28...
International audienceFor very high temperature reactors, the high level operating temperature of th...
A first principles thermodynamic model for nuclear fuel is in an advanced stage of development. This...
Oxidation of UO2 fuel under off-normal and normal reactor conditions occurs when fuel cladding fails...
International audienceFission gases production and release have a large impact on uranium dioxide fu...
Spent nuclear fuel from commercial reactors is comprised of 95-99 percent UO{sub 2} and 1-5 percent ...
ABSTRACT For Very High Temperature Reactors (V-HTR), the study of the Uranium-Carbon-Oxygen system i...
The objective of the Fuel Cycle R&D Program, Advanced Fuels campaign is to provide the research ...
The emission of uranium and ruthenium oxides from overheated nuclear fuel is a complex phenomenon wh...
Literature values and estimated data for the thermodynamics of the actinide oxides and fission produ...
Metal oxides added to UO2 to improve material performance during irradiation, or as burnable absorb...
The evolution of fission products from UO/sub 2/ during irradiation at high temperatures is of prima...
An analytical approach is proposed which allows the bunnup (by fission) of uranium required to cause...
Supported by results of calculations performed with two analytical tools (MFPR, which takes account ...
International audienceThermo-Desorption Spectrometry (TDS) was employed to study the release of fiss...
A series of hot-cell tests was conducted with UO{sub 2} that had been irradiated to an average of 28...
International audienceFor very high temperature reactors, the high level operating temperature of th...
A first principles thermodynamic model for nuclear fuel is in an advanced stage of development. This...
Oxidation of UO2 fuel under off-normal and normal reactor conditions occurs when fuel cladding fails...
International audienceFission gases production and release have a large impact on uranium dioxide fu...
Spent nuclear fuel from commercial reactors is comprised of 95-99 percent UO{sub 2} and 1-5 percent ...
ABSTRACT For Very High Temperature Reactors (V-HTR), the study of the Uranium-Carbon-Oxygen system i...
The objective of the Fuel Cycle R&D Program, Advanced Fuels campaign is to provide the research ...
The emission of uranium and ruthenium oxides from overheated nuclear fuel is a complex phenomenon wh...