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.

A method of decontaminating an object removed from a nuclear power plant utilizing a decontamination system is disclosed. The decontamination system includes a platform, an imaging system, a robotic arm including an end effector configured to discharge a decontamination medium, and a control system operably coupled to the imaging system and the robotic arm. The method includes placing the object on the platform, scanning, by the imaging system, the object, generating, by the control system, a three-dimensional model of the object based on the scanned object, planning, by the control system, a decontamination path based on the generated three-dimensional model, controlling, by the control system, a position of the robotic arm according to the planned decontamination path, and discharging, by the end effector, the decontamination medium onto the object at a plurality of positions along the planned decontamination path.

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.

An apparatus for treating waste of a nuclear reactor pressure vessel includes: a suction unit inserted into the nuclear reactor pressure vessel through a plurality of through-pipes passing through a lower portion of the nuclear reactor pressure vessel to suck waste inside the nuclear reactor pressure vessel; a waste treatment part connected to the suction unit to treat the waste; and a lower collection part connected to the waste treatment part to be positioned under the nuclear reactor pressure vessel with the suction unit therebetween.

An apparatus for treating waste of a nuclear reactor pressure vessel includes: a suction unit inserted into the nuclear reactor pressure vessel through a plurality of through-pipes passing through a lower portion of the nuclear reactor pressure vessel to suck waste inside the nuclear reactor pressure vessel; a waste treatment part connected to the suction unit to treat the waste; and a lower collection part connected to the waste treatment part to be positioned under the nuclear reactor pressure vessel with the suction unit therebetween.

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.

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.

Steel and/or copper spherical capsules are specifically engineered and manufactured for housing uranium waste products. The uranium waste products are placed within the spherical capsules. Human-made cavern(s) and/or substantially lateral wellbore(s) are constructed for receiving the uranium waste containing spherical capsules. The human-made cavern(s) and/or the substantially lateral wellbore(s) are deeply located in specific types of geologic rock formations thousands of feet below the Earth's surface. These uranium waste containing spherical capsules are loaded from the Earth's surface into the human-made cavern(s) and/or into the substantially lateral wellbore(s). The emplaced spherical capsules are surrounded by an immersive protective medium within the given human-made cavern(s) and/or within the substantially lateral wellbore(s). The given human-made cavern(s) and/or the given substantially lateral wellbore(s), with the uranium waste containing spherical capsules, are sealed off.

Methods for storing or disposing of nuclear waste include forming a drillhole that extends into the Earth from a terranean surface. The drillhole includes an entry at least proximate the terranean surface, a substantially vertical drillhole portion, and a hazardous material storage drillhole portion that is coupled to the substantially vertical drillhole portion and is formed in a subterranean salt formation. The methods further include moving a storage canister into the hazardous material storage drillhole portion. The storage canister is sized to fit from the drillhole entry through the substantially vertical drillhole portion, and into the hazardous material storage drillhole portion of the drillhole. The storage canister has an inner cavity that encloses nuclear waste material. The methods further include positioning a seal in the drillhole to isolate the hazardous material storage drillhole portion of the drillhole from the entry of the drillhole.

Methods for storing or disposing of nuclear waste include forming a drillhole that extends into the Earth from a terranean surface. The drillhole includes an entry at least proximate the terranean surface, a substantially vertical drillhole portion, and a hazardous material storage drillhole portion that is coupled to the substantially vertical drillhole portion and is formed in a subterranean salt formation. The methods further include moving a storage canister into the hazardous material storage drillhole portion. The storage canister is sized to fit from the drillhole entry through the substantially vertical drillhole portion, and into the hazardous material storage drillhole portion of the drillhole. The storage canister has an inner cavity that encloses nuclear waste material. The methods further include positioning a seal in the drillhole to isolate the hazardous material storage drillhole portion of the drillhole from the entry of the drillhole.