Patent classifications
G21F5/002
Apparatus 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.
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.
RADIOACTIVE WASTE CANISTER SYSTEMS AND METHODS
A hazardous waste canister includes a housing that includes at least one open end and defines an interior volume; and an end cap sized and configured to attach to the at least one open end of the housing to enclose the interior volume. The housing is configured to enclose a plurality of nuclear waste forms within the interior volume, with at least one of the plurality of nuclear waste forms different than at least another of the plurality of nuclear waste forms.
RADIOACTIVE WASTE CANISTER SYSTEMS AND METHODS
A hazardous waste canister includes a housing that includes at least one open end and defines an interior volume; and an end cap sized and configured to attach to the at least one open end of the housing to enclose the interior volume. The housing is configured to enclose a plurality of nuclear waste forms within the interior volume, with at least one of the plurality of nuclear waste forms different than at least another of the plurality of nuclear waste forms.
AUTONOMOUS ANTI-POLLUTION LIQUID CONTAINER FOR ISOTOPE ANALYSING OF EARTH SCIENCE AREA
An autonomous anti-pollution liquid container for isotope analysis of earth science area, consisting of an outer protective sleeve (1), a liquid storage main body part (2), a stabilizer storage mechanism (3), a main body base part (4), a control display part (5), a main body inner cover mechanism (6) and a neutralizer storage and releasing mechanism (7). The autonomous anti-pollution liquid container for isotope analysing of earth science area has multiple functions of heating, refrigerating, heat preservation and the like, can monitor temperature and liquid amount in real time, and can autonomously operate to quickly neutralize and scrap a hazardous chemical agent in an emergency, thereby avoiding leakage of a hazardous article and environmental pollution, and making a logistics process safe and reliable.
Controlling the temperature of uranium material in a uranium enrichment facility
An apparatus arranged to control the temperature of uranium material in a uranium material storage container, comprising a thermal guide which wraps around an external surface of the uranium material storage container to cause the uranium material storage container to exchange heat energy with a heat transfer medium inside the thermal guide and a heat exchanger to heat or cool the heat transfer medium outside the thermal guide. A method of controlling the temperature of uranium material in a uranium material storage container is also described.
Controlling the temperature of uranium material in a uranium enrichment facility
An apparatus arranged to control the temperature of uranium material in a uranium material storage container, comprising a thermal guide which wraps around an external surface of the uranium material storage container to cause the uranium material storage container to exchange heat energy with a heat transfer medium inside the thermal guide and a heat exchanger to heat or cool the heat transfer medium outside the thermal guide. A method of controlling the temperature of uranium material in a uranium material storage container is also described.
Fuel salt shipping system
A fuel salt shipping system includes an outer container defining an outer containment volume and an inner container disposed within the outer containment volume, with the inner container defining an inner volume configured to contain a molten fuel salt. The inner container and the outer container cooperate to define an annulus region therebetween. The fuel salt shipping system further includes a fuel salt conduit penetrating the outer container and the inner container and fluidically coupling the inner volume to an external environment of the system. The fuel salt shipping system further includes a heating system including a heater disposed in the annulus space and configured to impart a heat output to the molten fuel salt of the inner volume and change a phase of the molten fuel salt held therein from a solid phase to a liquid phase.
FUEL SALT SHIPPING SYSTEM
A fuel salt shipping system includes an outer container defining an outer containment volume and an inner container disposed within the outer containment volume, and defining an inner volume configured to contain a molten fuel salt. The inner container and the outer container may cooperate to define an annulus region therebetween. The fuel salt shipping system may further include a fuel salt conduit penetrating the outer container and the inner container and fluidically coupling the inner volume to an external environment of the system. The fuel salt shipping system may further include a heating system including a heater disposed in the annulus space and configured to impart a heat output to the molten fuel salt of the inner volume and change a phase of the molten fuel salt held therein from a solid phase to a liquid phase.