A high temperature reaction process was involved with the dry treatment of spent nuclear fuels (SNFs). SNFs include various kinds of fission products and one of the significant elements is cesium because its isotopes emit high radioactivity and heat load. Therefore, the knowledge of its behavior during the high temperature process is important to design a reactor and estimate material flows connecting with other processes. The main constituent of SNFs is uranium and, therefore, it was the first step to identify cesium compounds which was stable with uranium oxide. The Tpp analyses were performed for three temperatures of 500, 1000, and 1400 degrees C which represented relatively a low, a moderate, and a high temperature condition, respectiv...
The thermal decomposition kinetics of UO 2 C 2 O 4 ·3H 2 O were studied by TG method in a flowing ni...
ABSTRACT For Very High Temperature Reactors (V-HTR), the study of the Uranium-Carbon-Oxygen system i...
The thermodynamic data for unirradiated dioxides in the U- ThPu-O system are briefly reviewed. Calcu...
Spent nuclear fuel from commercial reactors is comprised of 95-99 percent UO{sub 2} and 1-5 percent ...
The objective of the Fuel Cycle R&D Program, Advanced Fuels campaign is to provide the research ...
International audienceThe interactions of iodine and caesium in UO2 have been investigated. For this...
A first principles thermodynamic model for nuclear fuel is in an advanced stage of development. This...
Literature values and estimated data for the thermodynamics of the actinide oxides and fission produ...
A growing demand for energy supply worldwide, coupled with the necessity to reduce emission of green...
Portions of the cesium-uranium-oxygen system have been investigated between 873 and 1273/sup 0/K and...
We are performing a detailed study of the volatilization behavior of U, Pu and possibly Am and Np un...
International audienceFor very high temperature reactors, the high level operating temperature of th...
Characterization of the fuel debris has been required for decommissioning Fukushima Daiichi Nuclear ...
International audienceThe fuel of civil nuclear plants, UO2, melts at 3120 K. During an hypothetical...
The equation of state of reactor fuels is required up to very high temperatures in order to assess t...
The thermal decomposition kinetics of UO 2 C 2 O 4 ·3H 2 O were studied by TG method in a flowing ni...
ABSTRACT For Very High Temperature Reactors (V-HTR), the study of the Uranium-Carbon-Oxygen system i...
The thermodynamic data for unirradiated dioxides in the U- ThPu-O system are briefly reviewed. Calcu...
Spent nuclear fuel from commercial reactors is comprised of 95-99 percent UO{sub 2} and 1-5 percent ...
The objective of the Fuel Cycle R&D Program, Advanced Fuels campaign is to provide the research ...
International audienceThe interactions of iodine and caesium in UO2 have been investigated. For this...
A first principles thermodynamic model for nuclear fuel is in an advanced stage of development. This...
Literature values and estimated data for the thermodynamics of the actinide oxides and fission produ...
A growing demand for energy supply worldwide, coupled with the necessity to reduce emission of green...
Portions of the cesium-uranium-oxygen system have been investigated between 873 and 1273/sup 0/K and...
We are performing a detailed study of the volatilization behavior of U, Pu and possibly Am and Np un...
International audienceFor very high temperature reactors, the high level operating temperature of th...
Characterization of the fuel debris has been required for decommissioning Fukushima Daiichi Nuclear ...
International audienceThe fuel of civil nuclear plants, UO2, melts at 3120 K. During an hypothetical...
The equation of state of reactor fuels is required up to very high temperatures in order to assess t...
The thermal decomposition kinetics of UO 2 C 2 O 4 ·3H 2 O were studied by TG method in a flowing ni...
ABSTRACT For Very High Temperature Reactors (V-HTR), the study of the Uranium-Carbon-Oxygen system i...
The thermodynamic data for unirradiated dioxides in the U- ThPu-O system are briefly reviewed. Calcu...