Elongate capsules for housing waste are configured for disposal (placement) into wellbore(s) that are located in particular deep underground geologic formation(s). These capsules have opposing structures for physically linking multiple capsules together in an end-to-end fashion. These opposing end structures may include a stinger with pins at a top end of the capsule; and a J-slots structure at the bottom end of the capsule. The stinger with pins of a first capsule may be (removably) attached to the J-slots of a second capsule. Further, a retrieval-tool also has the J-slots structure at one end. The J-slots structure of the retrieval-tool may be configured to (removably) attach to a stinger with pins of a given capsule (which may be linked to other capsule(s)); and then the retrieval-tool may be used to retrieve the given capsule(s) from a given wellbore. Capsule retrieval systems and/or method may utilize such capsule(s) and the retrieval-tool.

Elongate capsules for housing waste are configured for disposal (placement) into wellbore(s) that are located in particular deep underground geologic formation(s). These capsules have opposing structures for physically linking multiple capsules together in an end-to-end fashion. These opposing end structures may include a stinger with pins at a top end of the capsule; and a J-slots structure at the bottom end of the capsule. The stinger with pins of a first capsule may be (removably) attached to the J-slots of a second capsule. Further, a retrieval-tool also has the J-slots structure at one end. The J-slots structure of the retrieval-tool may be configured to (removably) attach to a stinger with pins of a given capsule (which may be linked to other capsule(s)); and then the retrieval-tool may be used to retrieve the given capsule(s) from a given wellbore. Capsule retrieval systems and/or method may utilize such capsule(s) and the retrieval-tool.

An apparatus for supporting spent nuclear fuel including a plurality of wall plates arranged in an intersecting manner to define a basket apparatus extending along a longitudinal axis. The basket apparatus may include a plurality of fuel cells and a plurality of flux traps between adjacent fuel cells. A plurality of reinforcement members may be positioned in the flux traps and may extend between opposing ones of the wall plates that form the flux traps. Each of the wall plates may be a slotted wall plate. The slotted wall plates may be interlocked with one another to form the basket apparatus. Each of the slotted wall plates may include an upper edge, a lower edge, and a plurality of plate slots formed in each of the upper and lower edges. The plate slots of the slotted wall plates may receive intersecting slotted wall plates.

An apparatus for supporting spent nuclear fuel including a plurality of wall plates arranged in an intersecting manner to define a basket apparatus extending along a longitudinal axis. The basket apparatus may include a plurality of fuel cells and a plurality of flux traps between adjacent fuel cells. A plurality of reinforcement members may be positioned in the flux traps and may extend between opposing ones of the wall plates that form the flux traps. Each of the wall plates may be a slotted wall plate. The slotted wall plates may be interlocked with one another to form the basket apparatus. Each of the slotted wall plates may include an upper edge, a lower edge, and a plurality of plate slots formed in each of the upper and lower edges. The plate slots of the slotted wall plates may receive intersecting slotted wall plates.

A package for transporting and/or storing radioactive materials, comprises a cavity for housing radioactive materials, as well as a radiological protection device comprising radiological protection elements arranged in an annular space, at least two successive radiological protection elements along a given direction of the annular space, from a longitudinal direction and a circumferential direction, and a locking member designed to limit and/or prevent the distancing of the two radiological protection elements relative to one another in a given direction.

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, aluminum, 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, aluminum, copper, and the like. The invention makes it possible to increase the strength of a container for solid radioactive waste.

Open pit mine (OPM) structures are modified or built new for use in disposing of low-level radioactive/nuclear waste (LLW). A drainage system is added to the OPM to drain water, such as, but not limited to, rain water, out of a volume of the OPM and to a particular geologic zone located far below the OPM that is isolated away from the local water table. Cells are formed within the volume of the OPM that are configured to receive the LLW. Cells are added to the OPM from a bottom towards a top of the OPM. Void spaces around the LLW materials within the cells are filled in with a protective-medium to mitigate against radionuclide migration away from the LLW materials within the cells. The protective-medium may be a blend of carbon nanotubes and a foam cement slurry. The carbon nanotubes may be made from reacting ethylene with vermiculite.

Open pit mine (OPM) structures are modified or built new for use in disposing of low-level radioactive/nuclear waste (LLW). A drainage system is added to the OPM to drain water, such as, but not limited to, rain water, out of a volume of the OPM and to a particular geologic zone located far below the OPM that is isolated away from the local water table. Cells are formed within the volume of the OPM that are configured to receive the LLW. Cells are added to the OPM from a bottom towards a top of the OPM. Void spaces around the LLW materials within the cells are filled in with a protective-medium to mitigate against radionuclide migration away from the LLW materials within the cells. The protective-medium may be a blend of carbon nanotubes and a foam cement slurry. The carbon nanotubes may be made from reacting ethylene with vermiculite.

A method of fragmentation of elements of a nuclear reactor includes placement of elements inside a cask and subsequent cutting, the cask being perforated. Each element is lowered into the cask by a full internal height of the cask using a gripper having clamping jaws. The element is intercepted at an upper edge of the cask, lifted, and positioned using video surveillance and artificial lighting so that a hydraulic cutter is directly under the clamping jaws. The element is cut at a point corresponding to a level of the upper edge of the cask, separating from the element a fragment equal to the internal height of the cask. Then the upper part of the element remaining after cutting is lowered inside the cask by the full internal height of the cask and the cutting of the element into fragments is repeated until the element is fully cut to fragments.