The present invention relates to a mobile compacting and melting complex volume reduction system (1) of radioactive waste. The complex volume reduction system (1) includes a mobile vehicle (3); a volume reducing part (7) that is disposed at one side of the inside of a container (5) mounted on the vehicle (3), and that presses and compacts dry active waste; a melting part (9) that is disposed at one side of the inside of the container (5) to melt the dry active waste by heat of a high temperature; and an exhaust gas processing part (11) that is connected to the melting part (9) to exhaust discharged gas to the outside.

The present invention relates to a process for the decontamination of radioactively contaminated material comprising the steps of a) providing radioactively contaminated material in a decontamination bath (200), b) providing a reactor unit (107) comprising a first reactor chamber (102) connected to a second reactor chamber (103), c) electrolyzing water with a ph>7 in the first reactor chamber (102) and generating (H.sub.3O.sub.2).sub.n, d) generating nanobubbles in the electrolyzed water of the second reactor chamber (103), e) optionally repeating steps c) and d), f) applying pressure to the water which contains nanobubbles, g) transferring the pressurized water which contains nanobubbles to a decontamination bath (200) containing an α-ray generator and the radioactively contaminated materiel, h) charging the nanobubbles with the α-particles emitted by the α-ray generator, and i) bringing the charged nanobubbles in contact with the radioactively contaminated material in the decontamination bath (200).

The present invention relates to a process for the decontamination of radioactively contaminated material comprising the steps of a) providing radioactively contaminated material in a decontamination bath (200), b) providing a reactor unit (107) comprising a first reactor chamber (102) connected to a second reactor chamber (103), c) electrolyzing water with a ph>7 in the first reactor chamber (102) and generating (H.sub.3O.sub.2).sub.n, d) generating nanobubbles in the electrolyzed water of the second reactor chamber (103), e) optionally repeating steps c) and d), f) applying pressure to the water which contains nanobubbles, g) transferring the pressurized water which contains nanobubbles to a decontamination bath (200) containing an α-ray generator and the radioactively contaminated materiel, h) charging the nanobubbles with the α-particles emitted by the α-ray generator, and i) bringing the charged nanobubbles in contact with the radioactively contaminated material in the decontamination bath (200).

The present invention provides a biological microbial treating agent, for radioactive material removal, comprising at least one type of microorganism selected from Bacillus amyloliquefaciens KS-R01, Bacillus siamensis KS-R02, Bacillus velezensis KS-R03 and Bacillus tequilensis KS-R04.

The present invention provides a biological microbial treating agent, for radioactive material removal, comprising at least one type of microorganism selected from Bacillus amyloliquefaciens KS-R01, Bacillus siamensis KS-R02, Bacillus velezensis KS-R03 and Bacillus tequilensis KS-R04.

Dangerous, toxic, and/or radioactive volatiles are produced from nuclear fission, nuclear decay, and/or as a byproduct from vitrification of radioactive wastes. Such volatiles are treated during and after vitrification of the radioactive waste, to be converted into fixed-chemicals, that are retained in, on, and/or proximate to a cold-cap located vertically above vitrified melt. The cold-cap may have one or more volatile fixing additives (VFAs) for retaining the fixed-chemicals. The VFAs are located in and/or the cold-cap. The vitrification may occur within at least one human-made cavern. The human-made cavern may be located within a deep geologic rock formation. The deep geologic rock formation may be located at least 2,000 feet below a terrestrial surface of the Earth. The human-made cavern may be formed by first drilling a wellbore from the terrestrial surface to the deep geologic rock formation and then underreaming the wellbore into the deep geologic rock formation.

The present disclosure provides a solidifying method of a radionuclide. The solidifying method of the radionuclide includes operations of: providing a low melting point glass including Bi.sub.2O.sub.3, B.sub.2O.sub.3, ZnO and SiO.sub.2; providing a glass mixture mixing a mixture to be treated containing a hydroxide of radionuclide and BaSO.sub.4 and the low melting point glass; and heating the glass mixture.

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 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.