Systems and methods that facilitate the transmutation of long-lived radioactive transuranic waste into short-live radioactive nuclides or stable nuclides using pre-pulse lasers to irradiate carbon nanotubes (CNTs) saturated with tritium into ionized gas of carbon and tritium and a laser-driven particle beam to fuse with the tritium and generate neutrons.

A method for the radiological characterisation of the radiation listing of mercury, comprising the Steps: a. preparing a predefined quantity of mercury, b. evaporating at least one fraction of the prepared mercury, and c. the radioactive γ-radiation emitted by the gaseous mercury.

A method for the radiological characterisation of the radiation listing of mercury, comprising the Steps: a. preparing a predefined quantity of mercury, b. evaporating at least one fraction of the prepared mercury, and c. the radioactive γ-radiation emitted by the gaseous mercury.

The present invention relates to a method of altering the relative proportions of protons, deuterons and tritons in a sample using a membrane. The membrane comprises a 2D material and an ionomer. The invention also relates to a method of making said membranes.

The present invention relates to a method of altering the relative proportions of protons, deuterons and tritons in a sample using a membrane. The membrane comprises a 2D material and an ionomer. The invention also relates to a method of making said membranes.

A radioactive noble gas removal filter, a filter unit, and a nuclear reactor containment vessel vent system with improved durability are provided. The radioactive noble gas removal filter according to the present invention includes a polyimide film including a structural unit represented by general formula (1).

##STR00001##

A reactor containment vessel vent system continuously releases steam generated in a reactor containment vessel to the atmosphere even when a power supply is lost. In the reactor containment vessel vent system, the noble gas filter that allows steam to pass through but does not allow radioactive noble gases to pass through among vent gas discharged from the reactor containment vessel is provided at a most downstream portion of the vent line. An immediate upstream portion of the noble gas filter and the reactor containment vessel are connected to each other by the return pipe via the intermediate vessel. When the radioactive noble gases having pressure equal to or higher than predetermined pressure stay in the immediate upstream portion of the noble gas filter, the staying radioactive noble gases flows into the intermediate vessel by the relief valve. Thus, steam permeability is maintained and the system continuously releases the steam.

A reactor containment vessel vent system continuously releases steam generated in a reactor containment vessel to the atmosphere even when a power supply is lost. In the reactor containment vessel vent system, the noble gas filter that allows steam to pass through but does not allow radioactive noble gases to pass through among vent gas discharged from the reactor containment vessel is provided at a most downstream portion of the vent line. An immediate upstream portion of the noble gas filter and the reactor containment vessel are connected to each other by the return pipe via the intermediate vessel. When the radioactive noble gases having pressure equal to or higher than predetermined pressure stay in the immediate upstream portion of the noble gas filter, the staying radioactive noble gases flows into the intermediate vessel by the relief valve. Thus, steam permeability is maintained and the system continuously releases the steam.

The present invention relates to a method for reducing the HTO concentration in a tritium-containing aqueous solution. The present invention includes bringing water vapor or the like of a tritium-containing aqueous solution into contact with a porous material having pores in a pore diameter range of 500 Å or less, selectively occluding the HTO in the tritium-containing aqueous solution in the porous material, and obtaining a tritium-containing aqueous solution in which the HTO concentration thereof is reduced. The present invention relates to a device used for reducing the HTO concentration in a tritium-containing aqueous solution. The present invention includes a reservoir for a raw tritium-containing aqueous solution, a means for generating water vapor or the like of the tritium-containing aqueous solution, an occlusion means in which is accommodated a porous material having pores in a pore diameter range of 500 Å or less, and a means for recovering the tritium-containing aqueous solution in which the HTO concentration is reduced. The present invention furthermore includes a transfer means for transferring the water vapor or the like to the occlusion means, and a means for transferring the tritium-containing aqueous solution in which the HTO concentration is reduced from the occlusion means to a recovery means.

A passive venting arrangement for use in venting of gases produced by radioactive materials includes a source gas region for receiving the gases produced by the radioactive materials; a filter ullage region disposed above the source gas region and segregated therefrom except for a plurality of bore holes which each extend between, and fluidly couple, the source gas region and the filter ullage region; and a plurality of filters disposed in contact with the filter ullage region, wherein each filter is structured to provide for the exchange of gases from the filter ullage region through the filter to an ambient environment.