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.

A compression member for insertion into a pig for transporting a container of biohazardous materials includes a flange maintained in spaced relation with an annulus by pillars; and spaced apart pivotable grip components supported by the annulus and extending downwards from the annulus between respective ones of the pillars towards, but not into contact with, the flange, the pivotable grip components resiliently compressible inwardly against the container when the container is received within the compression member. In use, the compression member receives at least a closure portion of the container and, in turn, is itself received within a complementary annulus of the pig. When being received within the complementary annulus of the pig, the pivotable grip components are urged inwards towards the container thereby to grip the container and provide a spacer for between this portion of the container and the pig.

A compression member for insertion into a pig for transporting a container of biohazardous materials includes a flange maintained in spaced relation with an annulus by pillars; and spaced apart pivotable grip components supported by the annulus and extending downwards from the annulus between respective ones of the pillars towards, but not into contact with, the flange, the pivotable grip components resiliently compressible inwardly against the container when the container is received within the compression member. In use, the compression member receives at least a closure portion of the container and, in turn, is itself received within a complementary annulus of the pig. When being received within the complementary annulus of the pig, the pivotable grip components are urged inwards towards the container thereby to grip the container and provide a spacer for between this portion of the container and the pig.

A containment enclosure for shielding an outer cask containing an inner canister loaded with nuclear waste such as spent fuel rods. The enclosure includes a lower base portion at least partially embedded in a concrete pad and an upper radiation shielding portion defined by a shield jacket coupled to and supported by the lower base portion at a circumferential joint. Cavities of the base and shielding portions collectively define a contiguous containment space for the cask. A portion of the cask resides in each of the base and shielding portions which completely enclose and shield the cask to minimize radiation dosage of personnel in the environment surrounding the cask. The cask is cooled by a natural convectively-driven ambient cooling air ventilation system including air inlets at the circumferential joint of the enclosure. The concrete pad may be part of a spent nuclear fuel storage installation comprising plural cask containment enclosures.

A containment enclosure for shielding an outer cask containing an inner canister loaded with nuclear waste such as spent fuel rods. The enclosure includes a lower base portion at least partially embedded in a concrete pad and an upper radiation shielding portion defined by a shield jacket coupled to and supported by the lower base portion at a circumferential joint. Cavities of the base and shielding portions collectively define a contiguous containment space for the cask. A portion of the cask resides in each of the base and shielding portions which completely enclose and shield the cask to minimize radiation dosage of personnel in the environment surrounding the cask. The cask is cooled by a natural convectively-driven ambient cooling air ventilation system including air inlets at the circumferential joint of the enclosure. The concrete pad may be part of a spent nuclear fuel storage installation comprising plural cask containment enclosures.

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 tamper-indicating assembly for a drum enclosure assembly is provided. The tamper-indicating assembly includes a tamper-indicating device that defines a cavity sized to receive and surround at least a portion of the closure bolt, the first flanged end, and the second flanged end to prevent movement of the closure bolt. A tab extends radially outward from the tamper-indicating device with respect to an axial centerline of the tamper-indicating assembly. The tamper-indicating assembly further includes a pin non-removably coupled to the tamper-indicating device. The pin extends through the tamper-indicating device and across the cavity such that the tamper-indicating device and the pin collectively surround the closure bolt. The exemplary tamper-indicating device described herein includes features that facilitate the robotic application of the tamper-indicating device to a drum enclosure.