The oxygen-to-metal atom ratio, or O/M, of solid solution uranium- plutonium oxide reactor fuel is a measure of the concentration of crystal defects in the oxide which affect many fuel properties, particularly, fuel oxygen potential. Fabrication of a high-temperature oxygen electrode, employing an electro-active tip of oxygen-deficient solid-state electrolyte, intended to confirm gaseous oxygen potentials is described. Uranium oxide and plutonium oxide O/M reference materials were prepared by in situ oxidation of high purity metals in the thermobalance. A solid solution uranium-plutonium oxide O/M reference material was prepared by alloying the uranium and plutonium metals in a yttrium oxide crucible at 1200$sup 0$C and oxidizing with moist...
International audienceInnovative americium-bearing uranium–plutonium mixed oxides U$_{1–y}$Pu$_y$O$_...
International audienceDiffusion mechanisms occurring during the sintering of oxide ceramics are affe...
Oxygen partial pressures in equilibria with nonstoichiometric solid solutions having the general for...
A survey was made of methods potentially useful for the determination of the oxygen to metal ratio i...
The oxygen-to-metal (O/M) ratio is one of the most critical parameters of nuclear fuel fabrication, ...
The possibility of measuring the oxygen-metal ratio (O/M) of U-Pu mixed oxides by x-ray diffraction ...
Methods used for the determination of oxygen to uranium ratios has been collected and discussed. The...
The elemental and chemical composition of nuclear fuel pellets are key factors influencing the mater...
AN AUTOMATED VERSION OF THE ELECTROMOTIVE FORCE (EMF) CELL FOR THE DETERMINATION OF...
A compilation of available fundamental information concerning plutonium oxides. Methods of preparati...
Results for the radial distribution of the oxygen potential and stoichiometry of a PWR fuel with an ...
ABSTRACT- In a CANDU ® reactor, ceramic uranium dioxide (UO2) fuel pellets are contained in Zircaloy...
The objective of the Fuel Cycle R&D Program, Advanced Fuels campaign is to provide the research ...
The oxides of the transuranic elements have been the subject of numerous investigations since the di...
The gaseous oxidation of uranium and its alloys is a complex process. Material transport across the ...
International audienceInnovative americium-bearing uranium–plutonium mixed oxides U$_{1–y}$Pu$_y$O$_...
International audienceDiffusion mechanisms occurring during the sintering of oxide ceramics are affe...
Oxygen partial pressures in equilibria with nonstoichiometric solid solutions having the general for...
A survey was made of methods potentially useful for the determination of the oxygen to metal ratio i...
The oxygen-to-metal (O/M) ratio is one of the most critical parameters of nuclear fuel fabrication, ...
The possibility of measuring the oxygen-metal ratio (O/M) of U-Pu mixed oxides by x-ray diffraction ...
Methods used for the determination of oxygen to uranium ratios has been collected and discussed. The...
The elemental and chemical composition of nuclear fuel pellets are key factors influencing the mater...
AN AUTOMATED VERSION OF THE ELECTROMOTIVE FORCE (EMF) CELL FOR THE DETERMINATION OF...
A compilation of available fundamental information concerning plutonium oxides. Methods of preparati...
Results for the radial distribution of the oxygen potential and stoichiometry of a PWR fuel with an ...
ABSTRACT- In a CANDU ® reactor, ceramic uranium dioxide (UO2) fuel pellets are contained in Zircaloy...
The objective of the Fuel Cycle R&D Program, Advanced Fuels campaign is to provide the research ...
The oxides of the transuranic elements have been the subject of numerous investigations since the di...
The gaseous oxidation of uranium and its alloys is a complex process. Material transport across the ...
International audienceInnovative americium-bearing uranium–plutonium mixed oxides U$_{1–y}$Pu$_y$O$_...
International audienceDiffusion mechanisms occurring during the sintering of oxide ceramics are affe...
Oxygen partial pressures in equilibria with nonstoichiometric solid solutions having the general for...