Sodium-cesium trap systems and methods for the simultaneous removal of both sodium (Na) and cesium (Cs) in gas are provided. The trap system includes a contacting vessel having an inlet and an outlet with carrier gas channeled therethrough. A heating system maintains a temperature gradient across the contacting vessel between a first temperature at the inlet and a second temperature at the outlet such that sodium and cesium contained within the carrier gas are condensed into liquid and the carrier gas exiting the vessel is substantially free of sodium and cesium.

Sodium-cesium trap systems and methods for the simultaneous removal of both sodium (Na) and cesium (Cs) in gas are provided. The trap system includes a contacting vessel having an inlet and an outlet with carrier gas channeled therethrough. A heating system maintains a temperature gradient across the contacting vessel between a first temperature at the inlet and a second temperature at the outlet such that sodium and cesium contained within the carrier gas are condensed into liquid and the carrier gas exiting the vessel is substantially free of sodium and cesium.

Sodium-cesium trap systems and methods for the simultaneous removal of both sodium (Na) and cesium (Cs) in gas are provided. The trap system includes a contacting vessel having an inlet and an outlet with carrier gas channeled therethrough. A heating system maintains a temperature gradient across the contacting vessel between a first temperature at the inlet and a second temperature at the outlet such that sodium and cesium contained within the carrier gas are condensed into liquid and the carrier gas exiting the vessel is substantially free of sodium and cesium.

Sodium-cesium trap systems and methods for the simultaneous removal of both sodium (Na) and cesium (Cs) in gas are provided. The trap system includes a contacting vessel having an inlet and an outlet with carrier gas channeled therethrough. A heating system maintains a temperature gradient across the contacting vessel between a first temperature at the inlet and a second temperature at the outlet such that sodium and cesium contained within the carrier gas are condensed into liquid and the carrier gas exiting the vessel is substantially free of sodium and cesium.

Methods of controlling the reactivity of a molten salt fission reactor. The molten salt fission reactor comprises a core and a coolant tank (101), the core comprising fuel tubes (103) containing a molten salt fissile fuel, and the coolant tank containing a molten salt coolant (102), wherein the fuel tubes are immersed in the coolant tank. The methods comprise dissolving a neutron absorbing compound in the molten salt coolant, the neutron absorbing compound comprising a halogen and a neutron absorbing element. The first method further comprises reducing the neutron absorbing compound to a salt of the halogen and an insoluble substance comprising the neutron absorbing element, the halogen being fluorine or chlorine, wherein the insoluble substance is not volatile at a temperature of the coolant during operation of the reactor. In the second method the one or more neutron absorbing compounds are chosen such that reduction of the neutron absorbing capacity of the one or more neutron absorbing compounds due to absorption of neutrons compensates for a fall in reactivity of the core in order to control fission rates in the core. Apparatus for implementing the methods are also provided.

Methods of controlling the reactivity of a molten salt fission reactor. The molten salt fission reactor comprises a core and a coolant tank (101), the core comprising fuel tubes (103) containing a molten salt fissile fuel, and the coolant tank containing a molten salt coolant (102), wherein the fuel tubes are immersed in the coolant tank. The methods comprise dissolving a neutron absorbing compound in the molten salt coolant, the neutron absorbing compound comprising a halogen and a neutron absorbing element. The first method further comprises reducing the neutron absorbing compound to a salt of the halogen and an insoluble substance comprising the neutron absorbing element, the halogen being fluorine or chlorine, wherein the insoluble substance is not volatile at a temperature of the coolant during operation of the reactor. In the second method the one or more neutron absorbing compounds are chosen such that reduction of the neutron absorbing capacity of the one or more neutron absorbing compounds due to absorption of neutrons compensates for a fall in reactivity of the core in order to control fission rates in the core. Apparatus for implementing the methods are also provided.

Fission of uranium-235 produces a wide range of fission products. Of particular importance is the production of molybdenum-99 due to its uses in the medical field. Fission products can be extracted from a molten salt reactor through electrochemical deposition by utilizing an electrode submerged in the flow of irradiated molten salt. However, this is likely to disrupt the redox of the irradiated molten fuel leading to harmful corrosion of the reactor. The present invention utilizes three electrode sets to capture fission products from irradiated molten salt of a molten salt reactor, monitor the redox behavior of the irradiated molten salt, and maintaining the balance of uranium ions to avoid harmful corrosion to the reactor's core.

Fission of uranium-235 produces a wide range of fission products. Of particular importance is the production of molybdenum-99 due to its uses in the medical field. Fission products can be extracted from a molten salt reactor through electrochemical deposition by utilizing an electrode submerged in the flow of irradiated molten salt. However, this is likely to disrupt the redox of the irradiated molten fuel leading to harmful corrosion of the reactor. The present invention utilizes three electrode sets to capture fission products from irradiated molten salt of a molten salt reactor, monitor the redox behavior of the irradiated molten salt, and maintaining the balance of uranium ions to avoid harmful corrosion to the reactor's core.

This invention relates to a system for regulating a liquid in a circuit able to reverse the direction of the circulation, with the system comprising: a regulating valve comprising at least one inlet and one outlet and comprising a movable obturator the position of which makes it possible to adjust the flow rate of the liquid through the valve, an expansion reservoir in communication with the liquid flowing in the circuit and intended to contain liquid and a compensating gas, characterized in that: the expansion reservoir is connected to the circuit by the intermediary of the valve and in such a way that the expansion reservoir communicates with at least one from among the inlet and the outlet of the valve regardless of the position of the obturator, with the position of the obturator being independent of the pressure of the fluid in the expansion reservoir. The invention also relates to a circuit integrating this system as well as a use of this system.

This invention relates to a system for regulating a liquid in a circuit able to reverse the direction of the circulation, with the system comprising: a regulating valve comprising at least one inlet and one outlet and comprising a movable obturator the position of which makes it possible to adjust the flow rate of the liquid through the valve, an expansion reservoir in communication with the liquid flowing in the circuit and intended to contain liquid and a compensating gas, characterized in that: the expansion reservoir is connected to the circuit by the intermediary of the valve and in such a way that the expansion reservoir communicates with at least one from among the inlet and the outlet of the valve regardless of the position of the obturator, with the position of the obturator being independent of the pressure of the fluid in the expansion reservoir. The invention also relates to a circuit integrating this system as well as a use of this system.