G21F9/02

Treatment method of radioactive iodine-containing fluid

The present invention provides a treatment method of a radioactive iodine-containing fluid, comprising passing the radioactive iodine-containing fluid through an adsorbent for iodine consisting of a silver-containing binderless zeolite molded body having a silver content of 50 mass % or less, to adsorb the radioactive iodine on the adsorbent for iodine.

Treatment method of radioactive iodine-containing fluid

The present invention provides a treatment method of a radioactive iodine-containing fluid, comprising passing the radioactive iodine-containing fluid through an adsorbent for iodine consisting of a silver-containing binderless zeolite molded body having a silver content of 50 mass % or less, to adsorb the radioactive iodine on the adsorbent for iodine.

Radioactive Waste Recycling Plant

Recycling of low and medium radioactivity nuclear waste from VVER and RBMK reactors and other nuclear installations.

The invention uses a recycling plant consisting of a waste feed unit; a plasma shaft-type furnace with a melter in the hearth of the furnace and a slug discharge unit connected with a receiving tank for molten slug; an air supply unit delivering air to the furnace to a pyrolysis gas combustion chamber; an evaporative heat exchanger for sharp reduction of the flue gases temperature; a gas purification unit with a sock-type filter; a heat-exchanger and a scrubber; pumps and tanks for agents and recycled products; fittings; and at least, one control module which is electrically connected to the slug discharge control module, an interior environment control module, an equipment status control module and, at least, one gas analytical module.

Radioactive Waste Recycling Plant

Recycling of low and medium radioactivity nuclear waste from VVER and RBMK reactors and other nuclear installations.

The invention uses a recycling plant consisting of a waste feed unit; a plasma shaft-type furnace with a melter in the hearth of the furnace and a slug discharge unit connected with a receiving tank for molten slug; an air supply unit delivering air to the furnace to a pyrolysis gas combustion chamber; an evaporative heat exchanger for sharp reduction of the flue gases temperature; a gas purification unit with a sock-type filter; a heat-exchanger and a scrubber; pumps and tanks for agents and recycled products; fittings; and at least, one control module which is electrically connected to the slug discharge control module, an interior environment control module, an equipment status control module and, at least, one gas analytical module.

MANAGING VOLATILES IN NUCLEAR WASTE VITRIFICATION
20210287821 · 2021-09-16 ·

Dangerous, toxic, and/or radioactive volatiles are produced from nuclear fission, nuclear decay, and/or as a byproduct from vitrification of radioactive wastes. Such volatiles are treated during and after vitrification of the radioactive waste, to be converted into fixed-chemicals, that are retained in, on, and/or proximate to a cold-cap located vertically above vitrified melt. The cold-cap may have one or more volatile fixing additives (VFAs) for retaining the fixed-chemicals. The VFAs are located in and/or the cold-cap. The vitrification may occur within at least one human-made cavern. The human-made cavern may be located within a deep geologic rock formation. The deep geologic rock formation may be located at least 2,000 feet below a terrestrial surface of the Earth. The human-made cavern may be formed by first drilling a wellbore from the terrestrial surface to the deep geologic rock formation and then underreaming the wellbore into the deep geologic rock formation.

MANAGING VOLATILES IN NUCLEAR WASTE VITRIFICATION
20210287821 · 2021-09-16 ·

Dangerous, toxic, and/or radioactive volatiles are produced from nuclear fission, nuclear decay, and/or as a byproduct from vitrification of radioactive wastes. Such volatiles are treated during and after vitrification of the radioactive waste, to be converted into fixed-chemicals, that are retained in, on, and/or proximate to a cold-cap located vertically above vitrified melt. The cold-cap may have one or more volatile fixing additives (VFAs) for retaining the fixed-chemicals. The VFAs are located in and/or the cold-cap. The vitrification may occur within at least one human-made cavern. The human-made cavern may be located within a deep geologic rock formation. The deep geologic rock formation may be located at least 2,000 feet below a terrestrial surface of the Earth. The human-made cavern may be formed by first drilling a wellbore from the terrestrial surface to the deep geologic rock formation and then underreaming the wellbore into the deep geologic rock formation.

METHOD AND APPARATUS FOR REDUCING HTO CONCENTRATION IN HTO-CONTAINING AQUEOUS SOLUTION

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.

Graphene membrane

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.

Graphene membrane

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.

Nuclear power plant

The invention relates to a nuclear power plant including a containment vessel including a reactor pressure vessel for receiving fissionable nuclear fuel, an aerosol filter stage a pressure relief conduit through which a gas volume flow which is filtered in the aerosol filter stage is releasable to ambient through a pass through opening in the containment vessel, and an iodine filter stage through which the gas volume flow that is filtered in the aerosol filter stage is filterable before being released to the ambient, wherein the iodine filter stage is arranged within the containment vessel, characterized in that the aerosol filter stage and the iodine filter stage are connected with one another so that transferring the gas volume flow from the aerosol filter stage to the iodine filter stage is performed essentially at an identical pressure level.