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.

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.

Processes, systems, and methods for selectively regenerating an ion exchange resin generally comprises washing the ion exchange resin with an elution agent that encourages only selected contaminants, and especially selected radioactive isotopes, to disengage or decouple from the resin and enter solution in the elution agent, which thereafter is identified as the elution agent solution. The elution agent solution is then passed through a column of isotope-specific media (ISM). When the selected radioactive isotopes within the elution agent solution come into contact with the constituent media isotopes of the ISM, the selected radioactive isotopes are retained on the reactive surface areas of the ISM or within the interstitial spaces of the porous structures of the constituent media isotopes of the ISM. In some embodiments, the constituent media isotopes of the ISM are embedded, impregnated, or coated with the specific radioactive isotope that the particular ISM are adapted to separate.

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.

The present disclosure provides a method for pre-separating nuclides in spent fuel, comprising steps: S1. generating a temperature of 1200 to 1600? C. in a center of a fuel element, and at the same time introducing a cooling medium to an outer surface of the fuel element, to introduce a temperature difference to heat the fuel element; S2. soaking cooled spent fuel in an ionic liquid to selectively dissolve fission products and transuranic elements, so that the fission products and the transuranic elements are pre-separated from the spent fuel. The method achieves the effect of pre-separating part of the fission products and transuranic elements by physical methods, and solves the problem that homogenization in traditional post-processing technology causes obstacles to nuclide separation.

Provided is a long-lived fission product (LLFP) processing method using neutrons that enables generation of high-intensity neutrons using only an accelerator without a fast-neutron reactor or an accelerator-driven nuclear reactor and thereby enables efficient nuclear transmutation of long-lived fission products. In the processing method, neutron-containing primary particles such as deuterons are accelerated under specific conditions inside an FFAG accelerator (10) and are caused to collide with a plate-shaped target (18) to generate high-energy first neutrons that form a beam in a single direction through the break-up of the primary particles and low-energy diffuse second neutrons through excitation of atomic nuclei in the plate-shaped target. A first LLFP (20) is located in the direction of travel of the beam of the first neutrons and a second LLFP (24) is located in proximity to the plate-shaped target (18).

Methods for isolating Pb and/or Pb isotopes from various sources are provided. Compositions comprising Pb and/or Pb isotopes free of certain amounts of various contaminants are also provided.

A process for the recovery of a radioisotope from a waste resin of a nuclear power plant comprises the steps of: a) treating a waste resin loaded with at least one radioisotope with an organic acid or alkaline compound to release the at least one radioisotope and to obtain a process solution containing the at least one radioisotope; b) separating the at least one radioisotope from the process solution through a reaction specific to the radioisotope so as to obtain a treated process solution depleted of the at least one radioisotope, wherein said depleted process solution comprises the organic acid or alkaline compound and optionally a non-reacted radioisotope; c) reacting the organic acid or alkaline compound in the depleted process solution from step b) by thermal and/or photochemical oxidation to form gaseous reaction products; and d) reloading the waste resin with the reacted process solution from step c) to bind the non-reacted radioisotope on the waste resin. Further, an apparatus is provided to carry out the above method.

A process for the recovery of a radioisotope from a waste resin of a nuclear power plant comprises the steps of: a) treating a waste resin loaded with at least one radioisotope with an organic acid or alkaline compound to release the at least one radioisotope and to obtain a process solution containing the at least one radioisotope; b) separating the at least one radioisotope from the process solution through a reaction specific to the radioisotope so as to obtain a treated process solution depleted of the at least one radioisotope, wherein said depleted process solution comprises the organic acid or alkaline compound and optionally a non-reacted radioisotope; c) reacting the organic acid or alkaline compound in the depleted process solution from step b) by thermal and/or photochemical oxidation to form gaseous reaction products; and d) reloading the waste resin with the reacted process solution from step c) to bind the non-reacted radioisotope on the waste resin. Further, an apparatus is provided to carry out the above method.