A mobile reactor radiation shielding solution prevents activation of structural materials to reduce a radiation dosage risk to living organisms and accelerates timetables for transport. The shielding solution can include: in-vessel neutron shield, in-vessel shadow shield, transport shield, and module shadow shield. In-vessel neutron shield reduces and prevents the activation of the structural materials and significantly reduces the need for heavy shielding to shield against the gamma emissions from activated structural materials. In-vessel shadow shield provides neutron and gamma shielding between the reactor and a balance-of-plant (BOP) module and control system. In-vessel shadow shield is placed near the active nuclear core to minimize size of the shield while maximizing the protected arc to shield radiation workers while preparing the nuclear reactor for transport. Transport shield is used during transportation when living organisms come into proximity of the reactor. Module shadow shield shields reactor control components and BOP module during operation.

An on-body injector system includes a drug container assembly including a container, a seal member, and a sealing interface between the seal member and the container. The container includes an opening and the seal member at least partially covers the opening in the container. A fluid pathway assembly is coupled to the drug container assembly and includes a needle that is movable between a storage position, in which a point of the needle is spaced from the seal member, and a delivery position, in which the point of the needle is disposed at least partially through the seal member. A radiation generator is configured to emit rays of radiation to sterilize and/or disinfect the sealing interface. A barrier is disposed adjacent to the sealing interface and has an opening. At least a portion of the drug container assembly is positioned adjacent to the opening in the barrier.

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 composite panel for a toxic material encapsulation system, comprising a reinforcing structure extending within and integrally formed with a non-biodegradable thermoplastic polymer.

A composite panel for a toxic material encapsulation system, comprising a reinforcing structure extending within and integrally formed with a non-biodegradable thermoplastic polymer.

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.

A system for externally cooling a cask containing heat-emitting spent nuclear fuel includes the cask comprising a radiation shielding body defining an internal cavity configured to hold a canister containing the spent nuclear fuel. A continuously annular cooling jacket extends circumferentially around an external surface of the cask body. The cooling jacket may have a double shell construction including an internal cavity for a cooling medium which provides an external heat sink for absorbing heat radiated from the external wall surface of the cask generated by the spent nuclear fuel. The heat emitted by the spent nuclear fuel is absorbed by the cooling medium in the cooling jacket, thereby in turn cooling the cask. In one embodiment, the cooling medium may be dry ice which undergoes sublimation by absorbing the heat to change from solid to gaseous phase directly. The jacket may be formed of multiple segments.

A system for externally cooling a cask containing heat-emitting spent nuclear fuel includes the cask comprising a radiation shielding body defining an internal cavity configured to hold a canister containing the spent nuclear fuel. A continuously annular cooling jacket extends circumferentially around an external surface of the cask body. The cooling jacket may have a double shell construction including an internal cavity for a cooling medium which provides an external heat sink for absorbing heat radiated from the external wall surface of the cask generated by the spent nuclear fuel. The heat emitted by the spent nuclear fuel is absorbed by the cooling medium in the cooling jacket, thereby in turn cooling the cask. In one embodiment, the cooling medium may be dry ice which undergoes sublimation by absorbing the heat to change from solid to gaseous phase directly. The jacket may be formed of multiple segments.

An apparatus for supporting radioactive fuel assemblies, such as spent nuclear fuel. In one aspect, the apparatus is in the form of a fuel rack having adjustable height pedestals. In another aspect, the apparatus is a canister including a first pressure vessel forming a first cavity and a second pressure vessel forming a second cavity, the first pressure vessel located in the second cavity of the second pressure vessel. An inner surface of the second pressure vessel may be in continuous surface contact with an outer surface of the first pressure vessel to form a dual-walled canister.

An apparatus for supporting radioactive fuel assemblies, such as spent nuclear fuel. In one aspect, the apparatus is in the form of a fuel rack having adjustable height pedestals. In another aspect, the apparatus is a canister including a first pressure vessel forming a first cavity and a second pressure vessel forming a second cavity, the first pressure vessel located in the second cavity of the second pressure vessel. An inner surface of the second pressure vessel may be in continuous surface contact with an outer surface of the first pressure vessel to form a dual-walled canister.