The method according to the present invention comprises using a high-frequency vibrating stirrer that is confirmed to include a treatment tank I, a high-frequency vibrating motor 3 fixed to a table positioned above the treatment tank 1, two vibrating rods 4 extending toward the bottom of the treatment tank 1 and coupled to the table, and multistage vibrating blades 5 mounted to the lower parts of the vibrating rods 4 and surface-plated with palladium or platinum serving as a catalyst in element transmutation, characterized in that the high frequency vibrating motor 3 is controlled by an inverter 6 so as to vibrate the multistage vibrating blades 5 at a frequency of 100-170 Hz in an aqueous solution 2 containing an element to be transmuted in the treatment tank 1, thereby transmuting the element in the aqueous solution 2 into another element. By adding heavy water to the solution to be treated, the transmutation efficiency can be elevated. By adding tritium water with an appropriate concentration as a substitute for the heavy water, the element transmutation can be completed within a short period of time and, at the same time, the tritium water that is seemingly the main cause of radioactive contamination can be effectively utilized and the radioactivity thereof can be attenuated or detoxified.

The method according to the present invention comprises using a high-frequency vibrating stirrer that is confirmed to include a treatment tank I, a high-frequency vibrating motor 3 fixed to a table positioned above the treatment tank 1, two vibrating rods 4 extending toward the bottom of the treatment tank 1 and coupled to the table, and multistage vibrating blades 5 mounted to the lower parts of the vibrating rods 4 and surface-plated with palladium or platinum serving as a catalyst in element transmutation, characterized in that the high frequency vibrating motor 3 is controlled by an inverter 6 so as to vibrate the multistage vibrating blades 5 at a frequency of 100-170 Hz in an aqueous solution 2 containing an element to be transmuted in the treatment tank 1, thereby transmuting the element in the aqueous solution 2 into another element. By adding heavy water to the solution to be treated, the transmutation efficiency can be elevated. By adding tritium water with an appropriate concentration as a substitute for the heavy water, the element transmutation can be completed within a short period of time and, at the same time, the tritium water that is seemingly the main cause of radioactive contamination can be effectively utilized and the radioactivity thereof can be attenuated or detoxified.

Disclosed herein is a nuclear power plant main steam system that reduces the atmospheric discharge of radioactive materials generated in an accident. The system includes: a decontamination water tank containing decontamination water; and a connection pipe for connecting the decontamination water tank to a main steam pipe which connects a steam generator and a turbine. A main steam safety valve or a connection valve is provided as a three-way valve configured to discharge the generated steam to the atmosphere when an accident occurs within a design basis and to transfer the generated steam to the decontamination water tank when an accident involving damage to nuclear fuel occurs. The main steam system reduces discharge of radioactive materials to the atmosphere when a containment bypass accident (e.g., a steam generator tube rupture caused by high-temperature steam) occurs.

A method for reducing radiologically-contaminated waste is provided. The method comprises treating radiologically-contaminated surfaces and subsurfaces. The method comprises consolidating soil waste. The method comprises employing real-time scanning technology to classify waste based at least in part on a threshold of radiological contamination. The waste is sorted based on the classification. The waste is disposed of via at least one of different disposal routes, based at least in part on the classification.

A method for reducing radiologically-contaminated waste is provided. The method comprises treating radiologically-contaminated surfaces and subsurfaces. The method comprises consolidating soil waste. The method comprises employing real-time scanning technology to classify waste based at least in part on a threshold of radiological contamination. The waste is sorted based on the classification. The waste is disposed of via at least one of different disposal routes, based at least in part on the classification.

A method for the anaerobic cultivation of microorganisms includes providing an aqueous solution having a pH value of 4.5 to 7.5 in a container, adding a substrate in a first substrate dosage to the aqueous solution, adding further elements to the aqueous solution, adding an inoculant with microorganisms to the aqueous solution, hermetically sealing the container, varying a temperature in a range from 40 to 80 degrees Celsius, taking a reference liquid sample and determining a first concentration of organic substance in the reference liquid sample, taking another liquid sample and determining another concentration of organic substance in the further liquid sample after the expiration of the first waiting time, if the further concentration of organic substance is smaller than 10 percent of the first concentration of organic substance, adding substrate in another substrate dosage, repeating until a sufficient amount of biomass is present in the container.

Provided is a laser ablation system and method for decontamination of radioactive particles. The system includes a laser head assembly, comprising a laser for ablating radioactive particles from an underlying material, a shroud surrounding the laser for containing the ablated radioactive particles; and a suction nozzle for receiving an airflow from the shroud and releasing the airflow, wherein the airflow contains the ablated radioactive particles, and the waste management system for removing and containing the ablated radioactive particles, comprising a gas pulse regenerable filtration system for removing radioactive particles from the airflow and depositing them in a containment flask, and a vacuum for moving the airflow through the hose into the containment flask.

A process for chemical stabilization of a uranium carbide composite material: UC.sub.x+yC with x≧1 and y>0, placed in a stabilization chamber, comprises: a rise in chamber internal temperature for oxidation of the compound based on uranium carbide between approximately 380° C. and 550° C., the chamber being fed with a neutral gas; isothermal oxidative treatment at the oxidation temperature, the chamber being placed under O.sub.2 partial pressure; controlling completion of stabilization of the compound, comprising monitoring the amount of molecular oxygen consumed and/or carbon dioxide or carbon dioxide and carbon monoxide given off, until achievement of an input set-point value for the amount of molecular oxygen, of a minimum threshold value for the amount of carbon dioxide or minimum threshold values for the carbon dioxide and carbon monoxide. A device implements the process.

Systems and methods are disclosed for inspection, maintenance, debris removal, and cleaning of environments that may be difficult to access and hazardous. The system comprises a mast assembly, an arm assembly, a debris removal system, and a drive system. The mast assembly comprises an inner mast and an outer mast having a central axis about which the arm assembly revolves. The arm assembly provides support for the debris removal system. The debris removal system comprises a bucket tool, a plow tool, and one or more hoses for clearing and removing debris. The drive system comprises a plurality of one or more of cables, pulleys, rollers, and hoists to at least one of control motion of the arm assembly, raise and lower the inner mast, and position and control at least one of the bucket tool and the plow tool. The system is at least one of manually and automatically controlled.

Provided is a method of treating radioactive liquid waste which reduces the amount of radioactive waste to be generated and is capable of removing a radioactive nuclide from radioactive liquid waste to the extent that the concentration thereof is less than or equal to the measurement lower limit using a simple apparatus configuration. A filtration device is connected to a colloid removal device by a connection pipe. An adsorption tower positioned at the highest stream of an adsorption device is connected to the colloid removal device by a connection pipe. The colloid removal device includes an electrostatic filter. Respective adsorption towers in the adsorption device are sequentially connected by a pipe. A discharge pipe is connected to the adsorption tower positioned at the lowest stream of the adsorption device. Radioactive liquid waste, containing particles having a particle diameter of 1 μm or greater, negatively charged colloids, and a radioactive nuclide, is supplied to the filtration device. The particles having a particle diameter of 1 μm or greater are removed by the filtration device and the negatively charged colloids are removed by the electrostatic filter that is positively charged. The radioactive nuclide is removed by the adsorption tower.