An apparatus for treating waste of a nuclear reactor pressure vessel includes: a suction unit inserted into the nuclear reactor pressure vessel through a plurality of through-pipes passing through a lower portion of the nuclear reactor pressure vessel to suck waste inside the nuclear reactor pressure vessel; a waste treatment part connected to the suction unit to treat the waste; and a lower collection part connected to the waste treatment part to be positioned under the nuclear reactor pressure vessel with the suction unit therebetween.

A nuclear reactor dismantlement system according to an embodiment includes bio-protective concrete including a first space into which a reactor is inserted and a second space that is connected to the first space and is expanded in the first space, a moving device that is positioned in the second space and moves the reactor, and a cutting device that is positioned in the second space and cuts the reactor.

A nuclear dismantling system for dismantling equipment contaminated with radioactive contamination, including a dismantling apparatus to be operated remotely while in a nuclear facility and a control system communicatively coupled to the dismantling apparatus to control the dismantling apparatus remotely.

A system for preparing a container holding radioactive waste for dry storage. In one aspect, the invention can be a system for preparing a container having a cavity loaded with radioactive elements for dry storage, the system comprising: a gas circulation system comprising a condenser module, a desiccant module, and a gas circulator module; the gas circulation system configured to form a hermetically sealed closed-loop path when operably connected to the cavity of the container; and means for adding and removing the desiccant module as part of the hermetically sealed closed-loop path.

A system for preparing a container holding radioactive waste for dry storage. In one aspect, the invention can be a system for preparing a container having a cavity loaded with radioactive elements for dry storage, the system comprising: a gas circulation system comprising a condenser module, a desiccant module, and a gas circulator module; the gas circulation system configured to form a hermetically sealed closed-loop path when operably connected to the cavity of the container; and means for adding and removing the desiccant module as part of the hermetically sealed closed-loop path.

The invention relates to a method of decontaminating a metal surface, wherein the metal surface is located on a component within a nuclear plant, in particular within the cooling system of a nuclear power plant, and is covered with a metal oxide layer containing radioactive substances, and wherein the method comprises 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 as well as metal ions and the radioactive substances, and wherein the decontamination solution is passed over an ion exchanger to immobilize the metal ions and the radioactive substances. An oxidant selected from the group consisting of 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.

Apparatus for treating a source of radioactive emission, the apparatus including at least one reflecting means adapted to be in proximity to the source for receipt of the radioactive emission and to at least partially reflect received emission towards the source, thereby effecting reduction of the radioactive emission from the source.

Apparatus for treating a source of radioactive emission, the apparatus including at least one reflecting means adapted to be in proximity to the source for receipt of the radioactive emission and to at least partially reflect received emission towards the source, thereby effecting reduction of the radioactive emission from the source.

An apparatus for volume reduction of material removed from a hazardous environment. The apparatus includes a shielded housing for receiving a workpiece therein, at least one cutting unit having a cutting head operable for contactless cutting, and a drive unit for rotating the at least one cutting unit around a main axis so the cutting head cuts the workpiece.

The present invention relates to a cleaning composition for the decontamination of surfaces, in particular radioactive surfaces, and the related decontamination method.