The kinetics of concentrates of uranium monoxide-oxide dissolution process by nitric acid solutions of 5...9 mole/l in the range of 11...90 °C has been studied. It is stated that initial nitric acid concentration increasing results in some uranium dissolution degree increasing only at the first process stage. Temperature increasing significantly raises uranium dissolution degree at the first stage as well. Uranium dissolution degree increases for all studied temperatures with increasing of the process period. The main feature of the studied process is that while dissolving uranium monoxide-oxide the behavior of iron, molybdenum, silicon additives is adequate to that of uranium. The equation of the reducing sphere describes the uranium leach...
Le retraitement du combustible nucléaire irradié passe par une étape de séparation de l’uranium, du ...
A series of characterization and dissolution studies has been performed to define flowsheet conditio...
The precipitation and dissolution of uranium(VI) from aqueous solutions containing 10-3 M uranyl nit...
Methods for dissolving unirradiated uranium-molybdenum alloy reactcr fuels in nitric acid, nitric ac...
This article draws a state of knowledge of the dissolution of uranium dioxide in nitric acid media. ...
"October 16, 1963.""Reprinted from Journal of Applied Chemistry Published by the Society of Chemical...
AbstractThe data on the uranium metal corrosion rate in the solutions of nitric acid (0,1 – 4M) and ...
The processes of triuranium octoxide dissolution by nitric acid with and without addition of ammoniu...
Nuclear power has rapidly come to the forefront as a cheaper, more reliable fuel source to solve the...
AbstractThe focus of this paper is the chemistry of mixed uranium plutonium oxide (MOx,) in nitric a...
International audienceUO2 pellets were prepared by densification of oxides obtained from the convers...
La dissolution en milieu nitrique de combustibles usés présentant de fortes teneurs en plutonium con...
Although a spent nuclear fuel is composed of about 96 wt. % of UO2, its composition and microstructu...
AbstractChemical processes for the elaboration of uranium concentrate from uranium ore have been stu...
Forecasted increases in the use of nuclear technology for the production of electricity, which in tu...
Le retraitement du combustible nucléaire irradié passe par une étape de séparation de l’uranium, du ...
A series of characterization and dissolution studies has been performed to define flowsheet conditio...
The precipitation and dissolution of uranium(VI) from aqueous solutions containing 10-3 M uranyl nit...
Methods for dissolving unirradiated uranium-molybdenum alloy reactcr fuels in nitric acid, nitric ac...
This article draws a state of knowledge of the dissolution of uranium dioxide in nitric acid media. ...
"October 16, 1963.""Reprinted from Journal of Applied Chemistry Published by the Society of Chemical...
AbstractThe data on the uranium metal corrosion rate in the solutions of nitric acid (0,1 – 4M) and ...
The processes of triuranium octoxide dissolution by nitric acid with and without addition of ammoniu...
Nuclear power has rapidly come to the forefront as a cheaper, more reliable fuel source to solve the...
AbstractThe focus of this paper is the chemistry of mixed uranium plutonium oxide (MOx,) in nitric a...
International audienceUO2 pellets were prepared by densification of oxides obtained from the convers...
La dissolution en milieu nitrique de combustibles usés présentant de fortes teneurs en plutonium con...
Although a spent nuclear fuel is composed of about 96 wt. % of UO2, its composition and microstructu...
AbstractChemical processes for the elaboration of uranium concentrate from uranium ore have been stu...
Forecasted increases in the use of nuclear technology for the production of electricity, which in tu...
Le retraitement du combustible nucléaire irradié passe par une étape de séparation de l’uranium, du ...
A series of characterization and dissolution studies has been performed to define flowsheet conditio...
The precipitation and dissolution of uranium(VI) from aqueous solutions containing 10-3 M uranyl nit...