A nuclear fusion system includes: a muon generation unit for generating negative muons; a gas supply unit for circulating and supplying gaseous deuterium or gaseous deuterium-tritium mixture as raw material gas for a nuclear fusion reaction; and a Laval nozzle for accelerating the raw material gas to supersonic velocity including a flow regulation portion in which the muons are decelerated and a reaction portion in which the nuclear fusion reaction occurs, wherein an oblique shockwave, which is generated as a result of collision of a shock wave generator arranged inside the reaction portion and the raw material gas accelerated to supersonic velocity, converges on a center axis of the Laval nozzle, and thereby a high-density gas target is retained in a gas phase, and wherein the muons are introduced into the high-density gas target, and thereby the nuclear fusion reaction is caused to occur.

Disclosed herein is a method for preparing a matrix for vitrifying radioactive waste, including: grinding natural magmatic rocks; and melting the ground product at 1450-1500 C. for 3-4.5 h followed by moulding and annealing to produce the matrix. The matrix includes 45%-65% by weight of SiO.sub.2, 9%-18% by weight of Al.sub.2O.sub.3, 4%-12% by weight of CaO, 3%-10% by weight of MgO, 6%-16% by weight of Fe.sub.2O.sub.3+FeO, 2%-9% by weight of Na.sub.2O+K.sub.2O and 1%-5% by weight of TiO.sub.2. The matrix is doped with simulated radioactive waste, ground, melted, moulded and annealed to obtain a glass wasteform with good chemical and thermal stability.

A volume reduction treatment method able to reduce the volume of the final disposal waste of a spent uranium catalyst. As a result, the disposal cost of the spent uranium catalyst is able to be reduced and the utilization of waste repositories are able to be improved.

The invention relates to the field of environmental protection, more specifically to the field of processing radioactive waste, and can he used for the safe and effective handling of a large quantity of liquid radioactive waste of various activity levels that has been formed as the result of decontaminating protective equipment of boxes and chambers, and makes it possible to decrease the volume of stored waste by solidifying same and incorporating same into a ceramic matrix. For this purpose, radioactive solutions after decontamination of surfaces of protective equipment are evaporated as alkaline and acidic solutions containing sodium hydroxide, potassium permanganate, oxalic acid, and nitric acid until a solid residue forms, and are calcined, and the calcinate is mixed with components of a fusion mixture containing oxides of titanium, calcium, iron (III), zirconium, and manganese (IV) and aluminum in a specified ratio, and fused.

According to one aspect of the invention, a method to create a ceramic waste form from used nuclear fuel. An active metal salt waste, a rare earth metal waste, and raw materials are received. The active metal salt waste is combined with the rare earth metal waste, forming a waste salt. The waste salt is then heated to approximately 500 C. The raw materials are also heated to approximately 500 C. The waste salt and raw materials are then blended to form a homogenous waste mixture. The homogenous waste mixture is heated to a first predetermined temperature for a predetermined amount of time, creating a ceramic waste form. The ceramic waste form is cooled to a second predetermined temperature.

According to one aspect of the invention, a method to create a ceramic waste form from used nuclear fuel. An active metal salt waste, a rare earth metal waste, and raw materials are received. The active metal salt waste is combined with the rare earth metal waste, forming a waste salt. The waste salt is then heated to approximately 500 C. The raw materials are also heated to approximately 500 C. The waste salt and raw materials are then blended to form a homogenous waste mixture. The homogenous waste mixture is heated to a first predetermined temperature for a predetermined amount of time, creating a ceramic waste form. The ceramic waste form is cooled to a second predetermined temperature.

Provided herein is a process for removal of .sup.99Tc from liquid intermediate level waste (ILW) of spent fuel reprocessing including the steps of: adding HNO.sub.3 to ILW till the pH is 2 to destroy the carbonates, transferring the ILW derived of carbonates to a tank containing mild steel wool (msw) for 4 to 48 hrs, subjecting the ILW and MS Wool to the step of separation, discharging the supernatant solution free of .sup.99Tc and retaining the corrosion products (goethite(FeOOH/magnetite), subjecting the said corrosion products to the step of vitrification, and storing the said vitrified .sup.99Tc bearing waste.

A connection device is intended for connecting a container for processing waste by high-temperature heat treatment and/or by vitrification with at least one source of products containing the waste and intended to be processed in the container and with a gas-extraction device, the connection device including a cylindrical body including a bottom end intended to be connected to the container, a top end intended to be connected to the at least one source of products and an intermediate opening intended to be connected to the gas-extraction device. The connection device includes a connection element having an element permeable to gases, which extends coaxially with the cylindrical body. The connection element includes a top end located at the top end of the cylindrical body and a bottom section that extends vertically below the bottom end of the cylindrical body.

The invention relates to the field of environmental protection, more specifically to the field of processing radioactive waste, and can he used for the safe and effective handling of a large quantity of liquid radioactive waste of various activity levels that has been formed as the result of decontaminating protective equipment of boxes and chambers, and makes it possible to decrease the volume of stored waste by solidifying same and incorporating same into a ceramic matrix. For this purpose, radioactive solutions after decontamination of surfaces of protective equipment are evaporated as alkaline and acidic solutions containing sodium hydroxide, potassium permanganate, oxalic acid, and nitric acid until a solid residue forms, and are calcined, and the calcinate is mixed with components of a fusion mixture containing oxides of titanium, calcium, iron (III), zirconium, and manganese (IV) and aluminum in a specified ratio, and fused.

Processes, systems, and methods for selectively regenerating an ion exchange resin generally comprises washing the ion exchange resin with an elution agent that encourages only selected contaminants, and especially selected radioactive isotopes, to disengage or decouple from the resin and enter solution in the elution agent, which thereafter is identified as the elution agent solution. The elution agent solution is then passed through a column of isotope-specific media (ISM). When the selected radioactive isotopes within the elution agent solution come into contact with the constituent media isotopes of the ISM, the selected radioactive isotopes are retained on the reactive surface areas of the ISM or within the interstitial spaces of the porous structures of the constituent media isotopes of the ISM. In some embodiments, the constituent media isotopes of the ISM are embedded, impregnated, or coated with the specific radioactive isotope that the particular ISM are adapted to separate.