A dismantling and decontamination system of biodegradable concrete of a nuclear power plant according to an exemplary embodiment includes: a dismantling device for dismantling an in-core instrument installed under biodegradable concrete to form a lower penetrated part of the biodegradable concrete; a decontamination device inserted inside the biodegradable concrete for decontaminating radioactive waste of the inner wall of the biodegradable concrete; a waste receiving device movable through the lower penetrated part of the biodegradable concrete; and a blocking device for blocking the upper opening of the biodegradable concrete to block an outflow of the radioactive dust.

A method for decommissioning a nuclear facility includes: separating a nuclear reactor pressure vessel from biodegradable concrete; decommissioning a concrete structure; covering the biodegradable concrete; and decommissioning the biodegradable concrete.

A radioactive structure dismantling method of a heavy water reactor facility that includes a calandria including a main shell and a sub shell, a calandria vault that receives the calandria therein, and a cover assembly that covers the calandria according to an embodiment, includes: preparing dismantling of the calandria; dismantling a reactor pipe installed in the calandria; dismantling the cover assembly that covers the calandria; dismantling the calandria; and dismantling the calandria vault.

Sterile barriers or sterile drapes that can be used with medical devices, including hand-held or self-supported X-ray equipment, are described in this application. In particular, this application describes sterile drapes that can be used with a medical device, the drape comprising a closed end portion, a middle portion with a size sufficient to enclose a part of the medical device being used near a patient, and an open end portion, the end portion configured to be closed by a user once the middle portion encloses the part of the medical device being used near a patient, wherein the sterile drape creates a sterile barrier around substantially the entire medical device once the open end is closed. Using the sterile drape allows the medical device, such as a hand-held or self-supported X-ray device, to be used in a medical procedure that requires a sterile field near the patient without disrupting that sterile field. Other embodiments are described.

The present invention relates to a method for removing cesium in a clay mineral using hydrogen peroxide. According to the present invention, cesium in a clay mineral is removed using hydrogen peroxide, which serves to induce interlayer expansion of the clay mineral to allow a cation to easily enter an interlayer of the clay mineral, and thus cesium desorption efficiency can be further improved. Also, the method according to the present invention can be efficiently used to restore soil in residential areas widely contaminated with a radionuclide when a major accident such as Fukushima nuclear accident occurs as well as various sites of atomic energy facilities contaminated with a radionuclide. Also, since radiation-contaminated soil is treated with only hydrogen peroxide and cations, secondary environmental pollution caused by wastes can be significantly reduce and the waste disposing cost can also be saved.

A Process for uranium removal from near neutral aqueous solutions by freshly prepared fine ferrihydrite generated during ultrasonic assisted corrosion of mild steel wool is disclosed. The above process is a simple and scalable process which minimizes agglomeration and reduces likelihood of aging of the ferrihydrite.

A method includes: a pre-treatment step of mixing radiocontaminated grains and a sodium phosphate-based dispersant; and a decontamination step of mixing the radiocontaminated grains processed by the pre-treatment step and paper sludge-derived sintered carbonized porous grains so as to incorporate radioactive .sup.134Cs and .sup.137Cs of the radiocontaminated grains in the sintered carbonized porous grains.

The invention is intended for integrated decontamination of soils contaminated with mercury (amalgam) or/and radionuclides. Method for soil decontamination includes preparation of pulp by mixing soils with water at the soil sampling point with separation of fraction with fragments more than 100 mm in the pulp preparation module, disintegration of pulp and soil aggregates in the disintegration module with separation of plants residues and fraction with fragments more than 10 mm. Pulp thickening. In the hydroclassification module the pulp is separated into sand and fine particle fractions, the fine particle fraction goes to the dehydration module, designed as a concentrator, where it is thickened and dehydrated for further disposal. If mercury and amalgam are present in soils they are separated in the thickening module. Technical resultimplementation of a low-waste nonchemical technology for decontamination of soil from mercury, its water-insoluble forms, amalgam or/and radionuclides in a single technological process without equipment resetting, separation of metal mercury or its amalgam.

According to the present invention, a method which dissolves hydrogen in a liquid that includes a radioactive substance is able to reduce the amount of radioactivity of the liquid. With respect to this method, the radioactive substance may include radioactive cesium, and hydrogen may be dissolved in the liquid by mixing a substance that contains a radioactive substance with a hydrogen water that contains 1.0 ppm or more of hydrogen.

A decontamination apparatus for decontaminating an external surface is provided. The decontamination apparatus has a moveable platform and a containment structure mounted on the moveable platform. The containment structure has at least one aperture and a respective contact surface arranged around the perimeter of the aperture. The contact surface is arranged to make contact with the external surface to define a working volume, when the containment structure is positioned proximal to the external surface. The decontamination apparatus includes a decontamination device arranged to decontaminate the external surface. The decontamination device is arranged within the working volume and arranged to access the external surface through the at least one aperture. There is also a vacuum system for generating a partial vacuum in the containment structure to apply a suction force to the external surface.