A liquid metal cooled molten salt reactor having a liquid metal vessel connected to a gas chamber that is connected to a molten salt chamber that is connected with a hot liquid metal vessel. A fuel salt that is withdrawn from the fuel salt tank through a feeding tube into the molten salt chamber from which the fuel salt is withdrawn into a salt separator. A purging gas is inserted into the gas chamber and withdrawn. A liquid metal coolant is dispensed from the liquid metal vessel through a plurality of dispensing nozzles into the molten salt chamber. The liquid metal coolant flows through the molten salt into a hot liquid metal vessel and then through a liquid metal filter into a liquid metal pump. The liquid metal coolant flows through a thermal exchanger subsequently returning to the liquid metal vessel.

The invention relates to nuclear power engineering and is designed to improve the safety of nuclear power plants by providing the ability to retain the melt in the nuclear reactor vessel at different severity of accidents in both passive and active mode.

In-vessel melt retention system containing a reactor located in a cavity, a coolant circulation pump outside the reactor vessel and a storage tank, characterized in that the storage tank is located in the cavity under the reactor vessel head; there are additional sump tanks above the reactor vessel head to collect coolant in LOCAs, the storage tank is connected to the top of the sump tanks by coolant supply channels.

The in-vessel melt retention system can be applied in nuclear power plants of various types, and can increase their safety by providing melt retention in the reactor vessel in various types of accidents.

The invention relates to nuclear power engineering and is designed to improve the safety of nuclear power plants by providing the ability to retain the melt in the nuclear reactor vessel at different severity of accidents in both passive and active mode.

In-vessel melt retention system containing a reactor located in a cavity, a coolant circulation pump outside the reactor vessel and a storage tank, characterized in that the storage tank is located in the cavity under the reactor vessel head; there are additional sump tanks above the reactor vessel head to collect coolant in LOCAs, the storage tank is connected to the top of the sump tanks by coolant supply channels.

The in-vessel melt retention system can be applied in nuclear power plants of various types, and can increase their safety by providing melt retention in the reactor vessel in various types of accidents.

Combined cleanup and heat sink systems work with nuclear reactor coolant loops. Combined systems may join hotter and colder sections of the coolant loops in parallel with any steam generator or other extractor and provide optional heat removal between the same. Combined systems also remove impurities or debris from a fluid coolant without significant heat loss from the coolant. A cooler in the combined system may increase in capacity or be augmented in number to move between purifying cooling and major heat removal from the coolant, potentially as an emergency cooler. The cooler may be joined to the hotter and colder sections through valved flow paths depending on desired functionality. Sections of the coolant loops may be fully above the cooler, which may be above the reactor, to drive flow by gravity and enhance isolation of sections of the coolant loop.

Combined cleanup and heat sink systems work with nuclear reactor coolant loops. Combined systems may join hotter and colder sections of the coolant loops in parallel with any steam generator or other extractor and provide optional heat removal between the same. Combined systems also remove impurities or debris from a fluid coolant without significant heat loss from the coolant. A cooler in the combined system may increase in capacity or be augmented in number to move between purifying cooling and major heat removal from the coolant, potentially as an emergency cooler. The cooler may be joined to the hotter and colder sections through valved flow paths depending on desired functionality. Sections of the coolant loops may be fully above the cooler, which may be above the reactor, to drive flow by gravity and enhance isolation of sections of the coolant loop.

Combined cleanup and heat sink systems work with nuclear reactor coolant loops. Combined systems may join hotter and colder sections of the coolant loops in parallel with any steam generator or other extractor and provide optional heat removal between the same. Combined systems also remove impurities or debris from a fluid coolant without significant heat loss from the coolant. A cooler in the combined system may increase in capacity or be augmented in number to move between purifying cooling and major heat removal from the coolant, potentially as an emergency cooler. The cooler may be joined to the hotter and colder sections through valved flow paths depending on desired functionality. Sections of the coolant loops may be fully above the cooler, which may be above the reactor, to drive flow by gravity and enhance isolation of sections of the coolant loop.

Combined cleanup and heat sink systems work with nuclear reactor coolant loops. Combined systems may join hotter and colder sections of the coolant loops in parallel with any steam generator or other extractor and provide optional heat removal between the same. Combined systems also remove impurities or debris from a fluid coolant without significant heat loss from the coolant. A cooler in the combined system may increase in capacity or be augmented in number to move between purifying cooling and major heat removal from the coolant, potentially as an emergency cooler. The cooler may be joined to the hotter and colder sections through valved flow paths depending on desired functionality. Sections of the coolant loops may be fully above the cooler, which may be above the reactor, to drive flow by gravity and enhance isolation of sections of the coolant loop.

An example for continuous removal of fission products from a molten-salt fueled nuclear reactor enclosed in a reactor containment may include separating actinides from other fission products flowing out of the reactor, returning the separated actinides back to the reactor to be consumed, and removing the other fission products out of the containment while the reactor is operating. In various embodiments, the reactor can be a critical reactor, a subcritical (e.g., accelerator-drive) reactor, or another type of reactor.

A coating of niobium oxide, zirconium titanate, or nickel titanate is formed on at least a part of a surface of a jet pump member constituting a jet pump serving as a reactor internal structure of a boiling water reactor. Further, a solution containing, e.g., a niobium compound is applied to at least a part of the surface of the jet pump member constituting the jet pump, and the jet pump member coated with the solution is heat-treated to form a coating of, e.g., niobium oxide. With this configuration, the jet pump member constituting the jet pump of the boiling water reactor is provided such that deposition of crud can be sufficiently suppressed on the jet pump member.

A coating of niobium oxide, zirconium titanate, or nickel titanate is formed on at least a part of a surface of a jet pump member constituting a jet pump serving as a reactor internal structure of a boiling water reactor. Further, a solution containing, e.g., a niobium compound is applied to at least a part of the surface of the jet pump member constituting the jet pump, and the jet pump member coated with the solution is heat-treated to form a coating of, e.g., niobium oxide. With this configuration, the jet pump member constituting the jet pump of the boiling water reactor is provided such that deposition of crud can be sufficiently suppressed on the jet pump member.