In order to prepare a useful radioactive substance from radionuclides included in high-level radioactive waste and the like, an embodiment of the present invention provides a method for preparing a radioactive substance including a muon irradiation step for obtaining a first radionuclide by causing negative muons to be incident onto a radioactive target nuclide and triggering a nuclear muon capture reaction. The prepared radioactive substance includes at least one of the first radionuclide and a second radionuclide that is at least one type of a descendant nuclide obtained from the first radionuclide through radioactive decay. An embodiment of the present invention also provides the radioactive substance.

The method and system disclosed provides radionuclide contamination mitigation by applying an aqueous carrier solution comprising a cation to a surface bearing a radionuclide contaminant to cause the radionuclide contaminant to enter solution forming a laden solution, then contacting the laden solution with a sequestering agent to bind to the radionuclide contaminant to form a laden sequestering agent. The removal and sequestration of the radionuclide contaminant from the contaminated surface leads directly to a reduction in the amount of radiologically-impacted critical infrastructure and the environment. The method and system are able to be performed or utilized economically with materials quickly available in the event of a radiological dispersion event.

A chemical decontamination reagent containing a reducing agent, a reductive metal ion, and an inorganic acid is provided to remove a radioactive oxide layer on a metal surface. The reagent can dissolve the radioactive oxide layer on the metal surface effectively at a relatively low temperature and enables a simple process of contacting the reagent to the radioactive oxide, thus economically effective in terms of cost and time required for the process. Since the decontamination does not use a conventional organic chelating agent such as oxalic acid, but the reducing agent as a main substance, the residuals of the reducing agent remained after decontamination can be decomposed and removed with an oxidizing agent. Due to the easy decomposition with the chemical decontamination reagent, secondary wastes can be minimized and the radionuclides remained in the decontamination reagent solution can be removed effectively.

A device system for military and/or humanitarian operations, in particular a mobile decontamination system, comprises a plurality of power-operated units, accessory parts and operating supplies, which together determine a functional scope of the device system. The power-operated units, accessory parts and operating supplies are mounted on a base plate by means of a retaining structure, said base plate having a defined placement surface and anchoring elements. The anchoring elements enable detachable anchoring of the base plate together with the retaining structure to a transport means, in particular to a transport vehicle. The retaining structure is formed from a plurality of self-supporting, structurally identical, cuboid-shaped frames, which are arranged next to each other and/or on top of each other and are fastened to the base plate. The frames each have eight corner pieces and twelve edge profile elements, which together enclose a defined storage volume. The power-operated units, accessory parts and operating supplies are arranged in the defined storage volumes and, preferably, at least the majority of the power-operated units and operating supplies are retained in the frames even during operation of the device system.

A process for the recovery of a radioisotope from a waste resin of a nuclear power plant comprises the steps of: a) treating a waste resin loaded with at least one radioisotope with an organic acid or alkaline compound to release the at least one radioisotope and to obtain a process solution containing the at least one radioisotope; b) separating the at least one radioisotope from the process solution through a reaction specific to the radioisotope so as to obtain a treated process solution depleted of the at least one radioisotope, wherein said depleted process solution comprises the organic acid or alkaline compound and optionally a non-reacted radioisotope; c) reacting the organic acid or alkaline compound in the depleted process solution from step b) by thermal and/or photochemical oxidation to form gaseous reaction products; and d) reloading the waste resin with the reacted process solution from step c) to bind the non-reacted radioisotope on the waste resin. Further, an apparatus is provided to carry out the above method.

Provided is a high-pressure fluid discharge device in which a pipe, to which a nozzle is connected, is routed and a high pressure fluid transferred through the pipe is discharged from the nozzle, wherein the pipe is formed by alternately connecting first pipes and second pipes having a larger flow passage area than the first pipes.

The invention relates to a method for producing an aqueous foam comprising the following steps: (a) preparing a solution comprising at least one surfactant and at least one protic polar solvent, (b) bringing the solution into contact with a pressurised gas, whereby a two-phase mixture is obtained, and (c) injecting the two-phase mixture, whereby, after expansion or dispersion of the gas, the aqueous foam is obtained. According to the invention, the solution further comprises at least one gelling compound chosen from a non-nitrogenous polysaccharide and gelatin. The invention also relates to the aqueous foam obtained by such a method and to the uses of same, in particular in the fields of decontamination, the purification of effluents, or the defusing or containment of explosive devices or suspected explosive devices.

The invention relates to a method for producing an aqueous foam comprising the following steps: (a) preparing a solution comprising at least one surfactant and at least one protic polar solvent, (b) bringing the solution into contact with a pressurised gas, whereby a two-phase mixture is obtained, and (c) injecting the two-phase mixture, whereby, after expansion or dispersion of the gas, the aqueous foam is obtained. According to the invention, the solution further comprises at least one gelling compound chosen from a non-nitrogenous polysaccharide and gelatin. The invention also relates to the aqueous foam obtained by such a method and to the uses of same, in particular in the fields of decontamination, the purification of effluents, or the defusing or containment of explosive devices or suspected explosive devices.

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.

The systems with a combination of a) methods to orient and/or stabilize the radioactive material to a magnetic axis and b) a delivery or reflection method of particles at a specific angle relative to the induced orientation to improve the penetration of said particles past the electrons shell into the nucleus for nuclear decay at a rate faster than the standard half-life calculations or similar reflection methods and systems to redirect decay-expulsion particles back at the preferred angles that increase the target material decay rate. Includes methods of pre-preparation of material, and in production use to extend useful periods of materials such that disposal of used materials deeper in their life when it is already less radioactive.