The present invention relates to a method of separating radioactive elements from a mixture, wherein the mixture is treated with at least one alkanesulfonic acid and at least one further acid, selected from the group consisting of hydrochloric acid, nitric acid, amidosulfonic acid and mixtures thereof and also the use of at least one alkanesulfonic acid and at least one further acid for separating radioactive elements from mixtures comprising these.

A system for removing particulates of a fissile material includes first and second filtration paths. A first filter and a first valve are disposed in the first filtration path. A second filter and a second valve are disposed in the second filtration path. The first valve and the second valve are configured to switch between a dual open state and a mixed open/closed state. During the dual open state, the first valve and the second valve axe open to permit concurrent flows of the effluent gas through the first and second filtration paths. During the mixed open/closed state, one of the first valve and the second valve is open while the other of the first valve and the second valve is closed to permit the particulates on a corresponding one of the first filter and the second filter to be dislodged by a countercurrent flow of a purging gas.

This application discloses the method for separating element or isotopes such as protactinium and gallium and isotopes thereof from a corresponding mixture which method comprises contacting the mixture with a carbon-based separation material, wherein the carbon-based separation material selectively associates with the element or isotope thereof.

A loop dissolution system specifically suited for dissolving uranium compounds in an acidic bath that continually circulates the acid over the uranium compound to be dissolved. The dissolution system includes an upper material feed dissolution plate on which the material to be dissolved is fed, a lower mixing and dissolution ring and a drop pipe system connecting and establishing fluid communication between the upper material feed dissolution plate and the lower mixing and dissolution ring. A pump for circulating the acidic fluid has an intake from the lower mixing and dissolution ring and an outlet that directs a first portion of a fluid to the upper material feed dissolution plate and a second portion of the fluid back into the lower mixing and dissolution ring to circulate the material suspended in the fluid within the lower mixing and dissolution ring to promote turbulence and facilitate dissolution.

A single integrated system for recycling used nuclear fuel (UNF) emerging from a reactor has a decladding vessel separating fuel pellets from nuclear fuel rods via oxidation to produce U.sub.3O.sub.8. A fluorination vessel is coupled to the decladding vessel to remove hexafluorides from the U.sub.3O.sub.8 produced by the decladding vessel. An electrowinning vessel is coupled to the fluorination vessel removing plutonium and actinides via electrowinning.

A single integrated system for recycling used nuclear fuel (UNF) emerging from a reactor has a decladding vessel separating fuel pellets from nuclear fuel rods via oxidation to produce U.sub.3O.sub.8. A fluorination vessel is coupled to the decladding vessel to remove hexafluorides from the U.sub.3O.sub.8 produced by the decladding vessel. An electrowinning vessel is coupled to the fluorination vessel removing plutonium and actinides via electrowinning.

Decontamination method for a nuclear reactor design component, comprising treating the nuclear reactor design component with a low-temperature plasma under the flow of reactionless gas. A selected site on the surface of the design component is supplied to the electrode. Plasma discharge is ignited between the surface of the design component chosen as the cathode, and the electrode chosen as the anode. Operating parameters of the discharge effective to sputtering of the cathode are chosen. The cathode is sputtered. The electrode and a gas pipeline diverting inert gas from the discharge zone are cooled to a temperature sufficient for the precipitation of the sputtered atoms on the surface of the electrode and lines. After sputtering the cathode to the specified depth, the electrode is moved to a new area of treatment and the process steps are repeated until the complete treatment of the entire surface of the design component.

Disclosed herein are embodiments of an extractant that can be used for chromatographic isolation of radioisotopes and/or metal species. The extractant can be combined with a support medium to provide an extractant composition that selectively and efficiently binds particular radioisotopes and/or metal species. Also disclosed herein are embodiments of a method for using the disclosed extractant embodiments, as well as embodiments of a method for making the extractant and extractant composition.

Provided is a fission product processing method for selectively transmuting only a long-lived radionuclide from fission products. The method for processing radioactive waste includes the step of extracting, from the radioactive waste, the isotopes without isotope separation, the isotope elements including radionuclides of fission products and having a common atomic number, and the step of irradiating the isotopes with high-energy particles generated by an accelerator to produce nuclear transmutation of a long-lived radionuclide of the radionuclides into a short-lived radionuclide with a short half-life or a stable nuclide re-utilizable as a resource.

According to one aspect of the invention, a method to create a ceramic waste form from used nuclear fuel. An active metal salt waste, a rare earth metal waste, and raw materials are received. The active metal salt waste is combined with the rare earth metal waste, forming a waste salt. The waste salt is then heated to approximately 500 C. The raw materials are also heated to approximately 500 C. The waste salt and raw materials are then blended to form a homogenous waste mixture. The homogenous waste mixture is heated to a first predetermined temperature for a predetermined amount of time, creating a ceramic waste form. The ceramic waste form is cooled to a second predetermined temperature.