A method for decommissioning a heavy water reactor facility includes: removing the plurality of guide tubes from a plurality of through-holes; installing a plurality of shielding stoppers in the plurality of through-holes; removing the shielding stopper installed in one through-hole of the plurality of through-holes, and inserting a cutting device into a lower portion of the reactivity mechanism deck through the one through-hole to cut a connection portion between the reactivity mechanism deck and the calandria vault by using the cutting device; and separating the reactivity mechanism deck from the calandria vault.

A system for storing and monitoring nuclear waste. The system includes a storage borehole having an end segment configured to store nuclear waste in a subterranean storage site location having a shale rock layer. The layer has a measured fluid overpressure in a range corresponding to greater than hydrostatic pressure to less than a lithostatic pressure from overlying rock layers. The system also includes a monitoring borehole configured to reside in the layer with an end segment of the monitoring borehole in a vicinity of the end segment of the storage borehole. The measured fluid pressure at the end of the monitoring borehole is in the fluid overpressure range.

A tool for cleaning a pool, particularly in a radioactive environment. The tool comprises a liquid filtering device, a pump, and a tank. The tank comprises an inlet for liquid from the pool. The tank at least partly houses the filtering device and the pump. The filtering device is arranged between the inlet and the pump so as to fluidically connect said inlet and pump

A method of cleaning naturally occurring radioactive materials (NORMs) from filtration socks utilizes a system that is equipped with a centrifuge, a disposal well, a surfactant and heated water. Through oil production, filtration socks become saturated with oil and NORMs. Typically, the used filtration socks are disposed of in a radioactive landfill or other proper disposal means. Through the method of cleaning NORMs, the used filtration socks are placed into a washing drum within a centrifuge and agitated with a surfactant and heated water to extract the NORMs from the used filtration socks. The centrifuge is spun to eject the waste solution from the washing drum, where the waste solution is pumped out of the centrifuge and into a class II disposal well to properly dispose the NORMs and brine from oil production processes. Cleaned filtration socks are then reusable or disposable in a more convenient manner.

A method of cleaning naturally occurring radioactive materials (NORMs) from filtration socks utilizes a system that is equipped with a centrifuge, a disposal well, a surfactant and heated water. Through oil production, filtration socks become saturated with oil and NORMs. Typically, the used filtration socks are disposed of in a radioactive landfill or other proper disposal means. Through the method of cleaning NORMs, the used filtration socks are placed into a washing drum within a centrifuge and agitated with a surfactant and heated water to extract the NORMs from the used filtration socks. The centrifuge is spun to eject the waste solution from the washing drum, where the waste solution is pumped out of the centrifuge and into a class II disposal well to properly dispose the NORMs and brine from oil production processes. Cleaned filtration socks are then reusable or disposable in a more convenient manner.

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.

The invention provides a method for isolating scandium, the method having the steps of dissolving titanium nuclear targets to create a solution; contacting the solution with a resin so as to retain scandium on the resin and generate an eluent containing titanium; contacting the scandium-containing resin with acid of a first concentration to remove impurities from the resin; and contacting the scandium-containing resin with an acid of a second concentration to remove scandium from the resin.

The invention provides a method for isolating scandium, the method having the steps of dissolving titanium nuclear targets to create a solution; contacting the solution with a resin so as to retain scandium on the resin and generate an eluent containing titanium; contacting the scandium-containing resin with acid of a first concentration to remove impurities from the resin; and contacting the scandium-containing resin with an acid of a second concentration to remove scandium from the resin.

A method of decontaminating metal surfaces in a cooling system of a nuclear reactor comprises: an oxidation step, comprising at least one acidic oxidation step and at least one alkaline oxidation step wherein metal oxides and radioisotopes on the metal surfaces are contacted with aqueous permanganate oxidant solutions; followed by a decontamination step wherein an aqueous solution comprising oxalic acid, formic acid, citric acid, tartaric acid, picolinic acid, gluconic acid glyoxylic acid or mixtures thereof is used to dissolve at least part of the metal oxides and radioisotopes; and a cleaning step wherein radioisotopes are immobilized on an ion exchange resin; wherein at least one treatment cycle includes a high temperature oxidation step, wherein the permanganate oxidant solution is kept at a temperature of at least 100 C.

A suctionable gel for eliminating a contaminating species contained in an organic layer on the surface of a material, consisting of a colloidal solution comprising, preferably consisting of: 1 wt % to 25 wt %, preferably 5 wt % to 20 wt % based on the total weight of the gel, of at least one inorganic viscosifying agent; 13 wt % to 99 wt %, preferably 80 wt % to 95 wt % based on the total weight of the gel, of an organic solvent selected among the terpenes and the mixtures thereof; optionally, 0.01 wt % to 10 wt %, based on the total weight of the gel, of at least one dye and/or pigment; optionally 0.1 wt % to 2 wt %, based on the total weight of the gel, of at least one surfactant. The disclosure further relates to a decontamination method using the gel.