Method for long-term dry storage of spent nuclear fuel includes injecting the inert gas into a cavity formed in a cask between inner and outer lids under pressure greater than the pressure of the inert gas in the inner cavity of the cask in which the spent nuclear fuel is located. The cask contains a body with a spent nuclear fuel container placed in it, tight inner and outer lids forming a cavity into which the inert gas is pumped under pressure greater than the pressure in the inner cavity of the cask. The outer lid comprises a labyrinth hole closed with a flange and sealed with a gasket. The flange comprises an angle valve, to which at least two pressure sensors are connected. The angle valve and sensors are covered with a protective cover during long-term storage. The gasket is installed in an annular groove of the lower flange.

Method for long-term dry storage of spent nuclear fuel includes injecting the inert gas into a cavity formed in a cask between inner and outer lids under pressure greater than the pressure of the inert gas in the inner cavity of the cask in which the spent nuclear fuel is located. The cask contains a body with a spent nuclear fuel container placed in it, tight inner and outer lids forming a cavity into which the inert gas is pumped under pressure greater than the pressure in the inner cavity of the cask. The outer lid comprises a labyrinth hole closed with a flange and sealed with a gasket. The flange comprises an angle valve, to which at least two pressure sensors are connected. The angle valve and sensors are covered with a protective cover during long-term storage. The gasket is installed in an annular groove of the lower flange.

The present invention is directed to new and improved industrial containment bags wherein the improvement comprises providing methods and technologies for improving the integrity of such bags during processes designed for lifting, transporting storing and/or disposing of the same. In certain embodiments, the improvement includes providing methods and technologies for improving the sealing capabilities of the bag's closure systems. In other embodiments, the improvement includes providing methods and technologies for assessing the load balance of materials being contained in such industrial containment bags; and thereafter, compensating for any significant load imbalances. The present invention is also directed to methods of manufacturing, using, filling, lifting, transporting, storing, and/or disposing of such new and improved industrial containment bags.

A dry storage systems for radioactive nuclear waste materials may include a double-walled canister system. The canister system may include a canister having a tubular inner shell defining an internal cavity for storing nuclear waste material, a first lid sealably welded to a first end of the inner shell, a primary base plate defining a peripheral edge portion and having an annular closure flange, and an annular full thickness butt weld formed at an abutment joint between the annular closure flange and a second end of the inner shell. The inner shell, first lid, and first end closure may collectively define a sealed primary pressure retention barrier. A tubular outer shell may adjoin the inner shell. The outer shell may be welded to the canister to form a hermetically sealed secondary pressure retention barrier.

A dry storage systems for radioactive nuclear waste materials may include a double-walled canister system. The canister system may include a canister having a tubular inner shell defining an internal cavity for storing nuclear waste material, a first lid sealably welded to a first end of the inner shell, a primary base plate defining a peripheral edge portion and having an annular closure flange, and an annular full thickness butt weld formed at an abutment joint between the annular closure flange and a second end of the inner shell. The inner shell, first lid, and first end closure may collectively define a sealed primary pressure retention barrier. A tubular outer shell may adjoin the inner shell. The outer shell may be welded to the canister to form a hermetically sealed secondary pressure retention barrier.

The invention relates to the field of nuclear technology. A container for storing, transporting and disposal of solid radioactive waste comprises a cask made of reaction-sintered silicon carbide comprising free silicon in an amount of 3-30 wt. % with a layer of gas-phase silicon carbide deposited on the surface thereof. The outer layer of the cask is made of a metal foam with an open porosity of 60-70% and a pore size of 5-6 mm; the pores are filled with boron carbide powder having a dispersity of 40-50 μm, which protects the environment from nuclear radiation emitted by HLW. A canister made of stainless steel with a thickness of 1-1.5 mm and intended for receiving radioactive waste is placed inside the silicon carbide cask. A 5 mm gap between the inner surface of the silicon carbide cask and the stainless-steel canister is filled with boron carbide powder which protects the environment from nuclear radiation emitted by HLW. The silicon carbide cask is sealed with a cover made of silicon carbide using a reaction welding method. A metal foam used as the metal foam with open porosity is selected from a group of metals comprising titanium, aluminium, copper, and the like. The invention makes it possible to increase the strength of a container for solid radioactive waste.

The invention relates to the field of nuclear technology. A container for storing, transporting and disposal of solid radioactive waste comprises a cask made of reaction-sintered silicon carbide comprising free silicon in an amount of 3-30 wt. % with a layer of gas-phase silicon carbide deposited on the surface thereof. The outer layer of the cask is made of a metal foam with an open porosity of 60-70% and a pore size of 5-6 mm; the pores are filled with boron carbide powder having a dispersity of 40-50 μm, which protects the environment from nuclear radiation emitted by HLW. A canister made of stainless steel with a thickness of 1-1.5 mm and intended for receiving radioactive waste is placed inside the silicon carbide cask. A 5 mm gap between the inner surface of the silicon carbide cask and the stainless-steel canister is filled with boron carbide powder which protects the environment from nuclear radiation emitted by HLW. The silicon carbide cask is sealed with a cover made of silicon carbide using a reaction welding method. A metal foam used as the metal foam with open porosity is selected from a group of metals comprising titanium, aluminium, copper, and the like. The invention makes it possible to increase the strength of a container for solid radioactive waste.

A waste material depositing system for depositing waste material into a sub-seabed sediment of an ocean floor. There is a penetrator including a first disposal stage and a second disposal stage. The first disposal stage having an outer shell disposed about a cavity, the cavity being shaped and sized to receive a waste disposal canister. The second disposal stage being removably coupled to a top end of the first disposal stage by an automatic disengagement device, and having: an outer cylinder, a plurality of second disposal fins disposed along a length of the outer cylinder, and an arrestor system coupled to a top portion of the outer cylinder.

A waste material depositing system for depositing waste material into a sub-seabed sediment of an ocean floor. There is a penetrator including a first disposal stage and a second disposal stage. The first disposal stage having an outer shell disposed about a cavity, the cavity being shaped and sized to receive a waste disposal canister. The second disposal stage being removably coupled to a top end of the first disposal stage by an automatic disengagement device, and having: an outer cylinder, a plurality of second disposal fins disposed along a length of the outer cylinder, and an arrestor system coupled to a top portion of the outer cylinder.

A method of packaging a radioactive waste including the steps of: (a) providing a containment enclosure having (i) an outer polymeric fabric layer and (ii) an inner polymeric fabric layer, wherein the outer and inner polymeric fabric layers are thermally stable to −40° F.; (b) placing a radioactive waste within the inner polymeric fabric layer; and (c) closing an outer closeable flap on the outer polymeric fabric layer.