Provided is a method of treating radioactive liquid waste which reduces the amount of radioactive waste to be generated and is capable of removing a radioactive nuclide from radioactive liquid waste to the extent that the concentration thereof is less than or equal to the measurement lower limit using a simple apparatus configuration. A filtration device is connected to a colloid removal device by a connection pipe. An adsorption tower positioned at the highest stream of an adsorption device is connected to the colloid removal device by a connection pipe. The colloid removal device includes an electrostatic filter. Respective adsorption towers in the adsorption device are sequentially connected by a pipe. A discharge pipe is connected to the adsorption tower positioned at the lowest stream of the adsorption device. Radioactive liquid waste, containing particles having a particle diameter of 1 μm or greater, negatively charged colloids, and a radioactive nuclide, is supplied to the filtration device. The particles having a particle diameter of 1 μm or greater are removed by the filtration device and the negatively charged colloids are removed by the electrostatic filter that is positively charged. The radioactive nuclide is removed by the adsorption tower.

A reduced-temperature method for treatment of a fuel element is described. The method includes molten salt treatment of a fuel element with a nitrate salt. The nitrate salt can oxidize the outer graphite matrix of a fuel element. The method can also include reduced temperature degradation of the carbide layer of a fuel element and low temperature solubilization of the fuel in a kernel of a fuel element.

The group of inventions relates to constructing structures, such as the buildings of nuclear power plants, which are erected from monolithic blocks or slabs made of concrete or reinforced concrete. A block or a slab contains a built-in container with components for the sorption extraction, from water, of radionuclides or toxic substances. The container has elements for feeding-in contaminated water and for evacuating treated water. An erection method includes building a structure using the said blocks or slabs. A method for manufacturing a building block or slab includes forming a body out of concrete, embedding into same at least one container having water-treatment components, and having fittings or flanges for feeding-in contaminated water and for evacuating treated water. The invention provides for safe operations when erecting structures, and prevents the spread of radionuclides beyond the boundaries of a structure.

An organic iodine trapping apparatus and method efficiently traps organic iodine in a nuclear reactor container vessel. A liquid vessel contains a non-volatile liquid (e.g., ionic liquid or interfacial active agent solution) capable of decomposing organic iodine. An introduction pipe introduces a fluid containing organic iodine in the nuclear reactor container vessel to the non-volatile liquid. The non-volatile liquid is heated by heat in the nuclear reactor container vessel or reaction heat of the fluid in the nuclear reactor container vessel. Then, the trapping apparatus decomposes and traps the organic iodine. The organic iodine trapping method includes heating a non-volatile liquid capable of decomposing organic iodine by heat in the nuclear reactor container vessel or reaction heat of fluid in the nuclear reactor container vessel; making the fluid containing organic iodine pass through the heated non-volatile liquid; and decomposing and trapping the organic iodine in the non-volatile liquid.

The invention describes a filtering device configured to be arranged inside a fluid to be filtered and comprising at least one main filter and a filter holder supporting the main filter. The filtering device is configured to be moved inside the fluid, in such a way that when the filtering device is moved in a first movement direction, at least one part of the fluid passes through the main filter in a first filtering direction. The filtering device is configured in such a way as to prevent the fluid from passing through the main filter in a second filtering direction opposite to the first filtering direction when the filtering device is moved in a second movement direction opposite to the first movement direction. The invention also relates to a system including such a device and to methods using such a device.

The invention describes a filtering device configured to be arranged inside a fluid to be filtered and comprising at least one main filter and a filter holder supporting the main filter. The filtering device is configured to be moved inside the fluid, in such a way that when the filtering device is moved in a first movement direction, at least one part of the fluid passes through the main filter in a first filtering direction. The filtering device is configured in such a way as to prevent the fluid from passing through the main filter in a second filtering direction opposite to the first filtering direction when the filtering device is moved in a second movement direction opposite to the first movement direction. The invention also relates to a system including such a device and to methods using such a device.

The invention concerns an apparatus and a method for treating radioactive material (36), in particular for cleaning radioactive contaminated water. The apparatus comprises a process chamber (10) with a combustion zone (12) for generating an oxygen rich gas (34) and an oxidation zone (14), which is arranged to receive the oxygen rich gas (34) from the combustion zone (12). The process chamber (10) further comprises a feed opening (16) for feeding the radioactive material (36) into the oxidation zone (14) and the process chamber (10) is configured to use the oxygen rich gas (34) for oxidizing the radioactive material (36) to obtain oxidized material (38). The apparatus further comprises a separation device (50) operationally connected to an outlet of the process chamber (10) and configured to at least partly separate the oxidized material (38) into a gaseous fluid (56) and a non.sup.− gaseous residue (58). This way a greatly reduced volume of the radioactive material (36) is achieved, enabling safe and efficient handling and/or compact and space-saving disposal of the radioactive material (36).

The invention concerns an apparatus and a method for treating radioactive material (36), in particular for cleaning radioactive contaminated water. The apparatus comprises a process chamber (10) with a combustion zone (12) for generating an oxygen rich gas (34) and an oxidation zone (14), which is arranged to receive the oxygen rich gas (34) from the combustion zone (12). The process chamber (10) further comprises a feed opening (16) for feeding the radioactive material (36) into the oxidation zone (14) and the process chamber (10) is configured to use the oxygen rich gas (34) for oxidizing the radioactive material (36) to obtain oxidized material (38). The apparatus further comprises a separation device (50) operationally connected to an outlet of the process chamber (10) and configured to at least partly separate the oxidized material (38) into a gaseous fluid (56) and a non.sup.− gaseous residue (58). This way a greatly reduced volume of the radioactive material (36) is achieved, enabling safe and efficient handling and/or compact and space-saving disposal of the radioactive material (36).

An in-line dissolved gas removal membrane-based apparatus for removing dissolved hydrogen and fission gases from the letdown stream from a reactor coolant system.

An in-line dissolved gas removal membrane-based apparatus for removing dissolved hydrogen and fission gases from the letdown stream from a reactor coolant system.