Fabricating structural components for a spent nuclear fuel container using the steps of forming cylindrical or rectangular channels to produce a structural component for a spent nuclear fuel container and applying a coating that includes tantalum-based material to the cylindrical or rectangular channels.

A radioactive nuclear waste storage system includes a cask comprising a hermetically sealed internal cavity configured for holding the waste such as spent nuclear fuel submerged in an inventory of water. One or more pressure surge capacitors disposed inside the cask include a vacuum cavity evacuated to sub-atmospheric conditions prior to storage of fuel in the cask. At least one rupture disk seals a vacuum chamber inside each capacitor. Each rupture disk is designed and constructed to burst at a predetermined burst pressure level occurring inside the cask external to the capacitor. This allows excess cask pressure occurring during a high pressure excursion resulting from abnormal operating conditions to bleed into capacitor, thereby returning the pressure inside the cask to acceptable levels. In one embodiment, the capacitors are located in peripheral regions of the cask cavity adjacent to the circumferential wall of the cask body.

The present disclosure provides a linked antenna pair for a shipping container having a thermally insulated and electromagnetically shielded cavity for holding a payload. The linked antenna pair comprises a first antenna disposed inside the cavity, a second antenna disposed outside the cavity, and a feed line that electrically connects the first antenna to the second antenna.

A capsule for the transfer of a target material in a conveying system between a target irradiation station and a collecting station comprising: a beamline channel for the passage of an energetic beam irradiating the target material, a target holder holding the target material or a substrate backing the target material at a glancing angle with respect to the beamline channel axis, a degrader foil positioned across the beamline channel for degrading an energy of the energetic beam upstream of the target material, a target cooling inlet and a target cooling outlet for passage of a cooling fluid in a target cooling duct in a vicinity of the target holder such that the target material can be cooled during an irradiation, and a degrader foil cooling inlet and a degrader foil cooling outlet for passage of a cooling gas in a vicinity of the degrader foil.

An improved system for receiving and storing a radioactive salt solution includes a tank configured to receive the radioactive salt solution while preventing criticality accidents, a solution inlet for carrying the radioactive salt solution to the tank, an overflow bottle, and a cap sealing the top end of the tank. The cap includes a lateral wye fitting having a lateral pipe configured to direct the radioactive salt solution from the solution inlet into the tank, a vertical pipe configured to direct gases from the tank to a ventilation system, and an overflow line configured to carry excess radioactive salt solution from the tank to the overflow tank. An air gap between the lateral pipe and the solution inlet prevents backflow of the radioactive salt solution into the solution inlet. A control system includes a level switch configured to provide a signal that the tank contains a maximum volume of the radioactive salt solution, a first valve configured to terminate flow of the radioactive salt solution to the lateral pipe upon receipt of the signal from the level switch; and a second valve configured to allow flow of the radioactive salt solution from the tank to the overflow line.

Systems and methods for formulating a radioactive liquid using a disposable container are described. The disposable container includes a flexible sidewall defining an interior space for containing the radioactive liquid during formulation. The flexible sidewall is constructed of sterile, pyrogen-free material to prevent contamination of the radioactive liquid. The flexible sidewall includes a first portion and a second portion. The disposable container also includes an access port and a dispense port. The access port is defined by the first portion of the flexible sidewall to provide access to the interior space. The dispense port is defined by the second portion of the flexible sidewall for the radioactive liquid within the interior space to be dispensed through.

Systems and methods for formulating a radioactive liquid using a disposable container are described. The disposable container includes a flexible sidewall defining an interior space for containing the radioactive liquid during formulation. The flexible sidewall is constructed of sterile, pyrogen-free material to prevent contamination of the radioactive liquid. The flexible sidewall includes a first portion and a second portion. The disposable container also includes an access port and a dispense port. The access port is defined by the first portion of the flexible sidewall to provide access to the interior space. The dispense port is defined by the second portion of the flexible sidewall for the radioactive liquid within the interior space to be dispensed through.

A neutron shielding packing body configured to pack a semiconductor device is disclosed. The neutron shielding packing body reduces Total Ionizing Dose (TID) defects caused in the semiconductor device by collisions with neutrons during air transportation of the semiconductor device. The neutron shielding packing body includes hydrogen and boron.

A modular tube volume reduction assembly for use at a vacuum tube vehicle station is provided. The assembly includes a modular station vacuum tube having a tube volume and a plurality of cavities longitudinally formed around a circumference of the modular station vacuum tube, and a volume reduction assembly integrated with the modular station vacuum tube, where the volume reduction assembly includes a plurality of blocks longitudinally coupled to a cavity interior of each of the plurality of cavities. The assembly includes a control system coupled between the modular station vacuum tube and the blocks. The control system radially moves the blocks to and from a vehicle outer surface of a vacuum transport tube vehicle at the vacuum tube vehicle station. The assembly displaces the tube volume between a station wall and the vehicle outer surface, and reduces the volume to be evacuated at the vacuum tube vehicle station.

A modular tube volume reduction assembly for use at a vacuum tube vehicle station is provided. The assembly includes a modular station vacuum tube having a tube volume and a plurality of cavities longitudinally formed around a circumference of the modular station vacuum tube, and a volume reduction assembly integrated with the modular station vacuum tube, where the volume reduction assembly includes a plurality of blocks longitudinally coupled to a cavity interior of each of the plurality of cavities. The assembly includes a control system coupled between the modular station vacuum tube and the blocks. The control system radially moves the blocks to and from a vehicle outer surface of a vacuum transport tube vehicle at the vacuum tube vehicle station. The assembly displaces the tube volume between a station wall and the vehicle outer surface, and reduces the volume to be evacuated at the vacuum tube vehicle station.