Patent classifications
G21F5/002
APPARATUS AND METHOD FOR REMOVAL OF RADIONUCLIDES IN LIQUIDS
A vessel for removing radionuclides from a liquid. The vessel comprises a shielded housing comprising an outer shell and an inner shell disposed within the outer shell. The housing defines an ion exchange chamber between the inner and outer shells. The vessel also comprises an inlet fluidly coupled with the ion exchange chamber, the inlet being configured for fluid communication with a source of the liquid, and an outlet fluidly coupled with the ion exchange chamber, the outlet being configured for fluid communication with a destination of the liquid. The vessel further comprises a first fluid passage extending between an exterior of the vessel and the inner shell and a second fluid passage extending between the exterior of the vessel and the inner shell.
CONCRETE CASK
A concrete cask enabling suppression of occurrence of stress corrosion cracking (SCC) in a lid welded part of a canister. The concrete cask includes: a metal canister accommodating spent fuel; a concrete container body for accommodating the canister inside the container body; a cooling passage provided between the external peripheral surface of the canister and the internal peripheral surface of the container body, and allowing air for cooling the external peripheral surface of the canister to pass; and a top space provided between the top surface part of the canister, and the inside of a lid of the container body. A baffle plate for suppressing introduction of air rising through the cooling passage to the top space is provided.
CONCRETE CASK
A concrete cask enabling suppression of occurrence of stress corrosion cracking (SCC) in a lid welded part of a canister. The concrete cask includes: a metal canister accommodating spent fuel; a concrete container body for accommodating the canister inside the container body; a cooling passage provided between the external peripheral surface of the canister and the internal peripheral surface of the container body, and allowing air for cooling the external peripheral surface of the canister to pass; and a top space provided between the top surface part of the canister, and the inside of a lid of the container body. A baffle plate for suppressing introduction of air rising through the cooling passage to the top space is provided.
Hazardous Material Canister
A canister to store spent nuclear fuel in an underground repository includes a first end portion; a second end portion; and a middle portion attachable to the first and second end portions to define an interior volume of the housing that is sized to enclose at least one spent nuclear fuel assembly. The first and second end portions comprise shielding.
Hazardous Material Canister
A canister to store spent nuclear fuel in an underground repository includes a first end portion; a second end portion; and a middle portion attachable to the first and second end portions to define an interior volume of the housing that is sized to enclose at least one spent nuclear fuel assembly. The first and second end portions comprise shielding.
SYSTEM FOR STORING A RADIOACTIVE SALT SOLUTION
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.
SYSTEM FOR STORING A RADIOACTIVE SALT SOLUTION
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.
UF6 TRANSPORT AND PROCESS CONTAINER (30W) FOR ENRICHMENTS UP TO 20% BY WEIGHT
The invention relates to UF.sub.6 transport and process containers to store UF.sub.6 enriched up to 20 percent by weight .sup.235U in amounts up to 1,500 kg U. The containers include a shell, which has an integral heat exchanger positioned between the exterior and interior surfaces/substrates of the shell. The integral heat exchanger is composed of metal passage voids to pass heat transport fluid. The shell forms an inner chamber, and a partition configuration is positioned within the inner chamber, extending longitudinally along the length of the container, to form a plurality of individual compartments within the inner chamber to store the UF.sub.6. The containers may be produced by additive manufacturing methods.
UF6 TRANSPORT AND PROCESS CONTAINER (30W) FOR ENRICHMENTS UP TO 20% BY WEIGHT
The invention relates to UF.sub.6 transport and process containers to store UF.sub.6 enriched up to 20 percent by weight .sup.235U in amounts up to 1,500 kg U. The containers include a shell, which has an integral heat exchanger positioned between the exterior and interior surfaces/substrates of the shell. The integral heat exchanger is composed of metal passage voids to pass heat transport fluid. The shell forms an inner chamber, and a partition configuration is positioned within the inner chamber, extending longitudinally along the length of the container, to form a plurality of individual compartments within the inner chamber to store the UF.sub.6. The containers may be produced by additive manufacturing methods.
Lined hazardous materials container
Provided is a device and method for containing hazardous waste, including a container for hazardous waste, comprising a hangable bag having an interior volume, the hangable bag being constructed at least in part of collapsible material and configured to be lifted and configured to support an interior bladder, and the interior volume being variable; and an interior bladder, the interior bladder connectable with a through port to a lid.