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.

A molten salt reactor comprising a reactor vessel and a molten salt contained within the reactor vessel. There is a corrosion reduction unit configured to process the molten salt to maintain an oxidation reduction ratio, (E(o)/E(r)), in the molten salt at a substantially constant level, wherein E(o) is an element (E) at a higher oxidation state (o) and E(r) is the element (E) at a lower oxidation state (r).

A method for in-situ measuring of a liquidus temperature of a supply of the molten salt, includes withdrawing a sample of the molten salt from the supply, placing it into a sample container, and cooling the sample of the molten salt from a first temperature above the liquidus temperature of the molten salt to a second temperature at which at least a portion of the sample of the molten salt solidifies. The method includes taking a plurality of temperature measurements of the sample of the molten salt during cooling of the sample and determining the liquidus temperature of the molten salt from the measurements. The sample of the molten salt is heated from the second temperature to the first temperature and returned to the supply of the molten salt.

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.

A molten salt reactor includes a reactor vessel and a molten salt contained within the reactor vessel and undergoing a nuclear reaction. The molten salt includes insoluble metal fission products and dissolved gas fission products produced by the nuclear reaction. There is a separation unit configured to receive the molten salt and remove the insoluble metal fission products and dissolved gas fission products from the molten salt. The separation unit includes a laundering chamber into which the molten salt is introduced to form a froth containing the insoluble metal fission products and dissolved gas fission products. There is a filtration chamber, interconnected to the laundering chamber, configured to receive the froth from the laundering chamber and separate from the froth the insoluble metal fission products and dissolved gas fission products.

A molten salt reactor includes a reactor vessel and a molten salt contained within the reactor vessel and undergoing a nuclear reaction. The molten salt includes insoluble metal fission products and dissolved gas fission products produced by the nuclear reaction. There is a separation unit configured to receive the molten salt and remove the insoluble metal fission products and dissolved gas fission products from the molten salt. The separation unit includes a laundering chamber into which the molten salt is introduced to form a froth containing the insoluble metal fission products and dissolved gas fission products. There is a filtration chamber, interconnected to the laundering chamber, configured to receive the froth from the laundering chamber and separate from the froth the insoluble metal fission products and dissolved gas fission products.

The invention relates to a nuclear reactor operating according to the dual fluid principle with a special liquid metal fissionable mixture as liquid fuel in the liquid fuel line, which has a high percentage of actinoids, preferably 69% and higher. Preferred metals are selected from chromium (Cr), manganese (Mn) and iron (Fe). Preferred actinoids are selected from thorium (Th), uranium (U) and plutonium (Pu). The mixtures and resulting multicomponent alloys need not necessarily be an eutectic.