A method and apparatus for the electrochemical removal of material from a surface in which two or more fluid jets or flows are arranged to impinge on the surface of the object and an electrical current flows through one fluid flow path, through the object, and then through a second fluid flow path.

A process for recovering uranium from components contaminated with uranium oxide includes providing a cleaning apparatus with a cleaning solution for dissolving the uranium oxide of the components, carrying out a cleaning process by introducing a batch of components into the cleaning apparatus, and carrying out a measurement for determining the uranium content of the components. The cleaning and the measuring are repeated if a limit value for the uranium content is exceeded. The components are discharged from the process if the uranium content falls below a limit value. The cleaning is carried out on a plurality of successive batches of components until a control measurement indicates an unsatisfactory cleaning action of the cleaning solution. The uranium oxide dissolved in the cleaning solution is recovered after indication of the unsatisfactory cleaning action.

Devices for eliminating radioactive contamination of radioactive waste by providing adaptive processing of the decontamination solution for reuse. The plant for electrochemical decontamination of metal radioactive waste includes a pipe equipped with shut-off valves, a radioactive waste processing module that comprises a unit for electrochemical decontamination connected by a ventilation channel to the ventilation module and pipe for decontamination solution supply and discharge equipped with shut-off valves. The plant is equipped with a decontamination solution preparation module connected with a pipe for decontamination solution supply and discharge, at least one pump, while the module for decontamination solution receiving is equipped with devices for cleaning and pH correction of decontamination solution, and the unit for electrochemical decontamination of metal radioactive waste, the module for decontamination solution receiving and the decontamination solution preparation module are equipped with pH measurement elements.

A method for reducing radiologically-contaminated waste is provided. The method comprises treating radiologically-contaminated surfaces and subsurfaces. The method comprises consolidating soil waste. The method comprises employing real-time scanning technology to classify waste based at least in part on a threshold of radiological contamination. The waste is sorted based on the classification. The waste is disposed of via at least one of different disposal routes, based at least in part on the classification.

This invention generally concerns radioactive decontamination of deposits on components in a nuclear power plant and is specifically concerned with improved compositions, systems and methods for disrupting, dissolving, removing and reducing at ambient temperature radionuclides formed on the primary side surfaces of components in a pressurized water reactor and the internal components of a boiling water reactor. The methods include identifying the structure, taking the structure out of operational service, contacting the structure with an aqueous solution (e.g., a recirculating flow or static immersion), and adding an effective amount of elemental metal in solid form to the aqueous solution.

A method of decontaminating a metal surface located on a component within a nuclear plant, in particular within the cooling system of a nuclear power plant, which is covered with a metal oxide layer containing radioactive substances, the method including a decontamination step in which a metal oxide layer pretreated in an oxidation step is contacted with an aqueous solution of an organic acid to dissolve the metal oxide layer, forming a decontamination solution containing the organic acid, metal ions and the radioactive substances, and passing the decontamination solution over an ion exchanger to immobilize metal ions and radioactive substances. An oxidant selected from oxygen, air, hydrogen peroxide and ozone is dosed into the decontamination solution to control the dissolution rate of the metal oxide layer. The method is particularly suitable for large-scale system decontamination and ensures high process stability.

An electrolytic treatment system to decontaminate the surface of a radioactively contaminated metallic workpiece has at least two electrodes in close proximity to the surface but not in direct electrical contact. The electrodes are separated from the surface by an electrolyte. Insulation is provided in the electrolyte between the electrodes to avoid or minimize a direct current path between the electrodes though the electrolyte.

An apparatus (10) is described for removing radioactive contamination, at least in part, from a first article (A1) comprising a metal, preferably wherein the metal comprises and/or is a low melting point metal for example lead and/or an alloy thereof. The apparatus (10) comprises a heated first vessel (100A) for melting the metal, at least in part, therein, thereby providing a melt (M) therefrom. The apparatus (10) comprises casting means (200) for forming a second article (A2), particularly a sheet, having a predetermined thickness (T), from the melt, preferably wherein the casting means (200) comprises and/or is a rotatable roller (210) arrangeable to contact the melt (M) to thereby form thereon the second article (A2) and a guide (220) arranged to remove the second article (A2) from the roller (210). The apparatus (10) comprises a set of radiation detectors (300), including a first radiation detector (300A), arranged to detect a first fraction of the radioactive contamination, if present, in a first part (P1) of a set of parts of the second article (A2), preferably wherein the set of radiation detectors (300) comprises opposed first and second radiation detectors (300A, 300B) arranged to receive the second article (A2) traversing therebetween. The apparatus (10) comprises a cutter (400) arrangeable to excise the first part (P1) of the second article (A2) therefrom.

In a submersible ultrasonic cleaning system for use in highly radioactive environments (e.g., cleaning radiated nuclear fuel assemblies), a bond between energy producing transducers and an radiating wall is strengthened with a polyurethane adhesive such as Permabond PT326, or 3M DP-190 adhesive. In various diagnostic tests, one or more of the transducers are operated in an energy-transmitting mode while one or more other transducers are operated in an energy-detecting mode to detect a weakened transducer/wall bond and/or acoustic conditions of the working fluid.

An electrolyte for electrochemical decontamination and a preparation method and application thereof. The electrolyte is an aqueous solution including the following solutes: phosphoric acid, oxalic acid, citric acid, tartaric acid, hydrogen peroxide and glacial acetic acid. The electrolyte has a good decontamination effect and allows for fast decontamination and is obtained by reasonably combining different types of solutes and controlling the levels of the solutes and resulting secondary waste solution and residues are easy to treat. The electrolyte is suitable for overall or local electrochemical decontamination of radioactively contaminated stainless steel scrap.