Nuclear reactor systems and associated devices and methods are described herein. A representative nuclear reactor system includes a reactor vessel having a barrier separating a core region from a shield region. A plurality of fuel rods containing a liquid nuclear fuel are positioned in the core region. A liquid moderator material is also positioned in the core region at least partially around the fuel rods. A plurality of heat exchangers can be positioned in the shield region, and a plurality of heat pipes can extend through the barrier. The moderator material is positioned to transfer heat received from the liquid nuclear fuel to the heat pipes, and the heat pipes are positioned to transfer heat received from the moderator material to the heat exchangers. The heat exchangers can transport the heat out of the system for use in one or more processes, such as generating electricity.

Nuclear reactor systems and associated devices and methods are described herein. A representative nuclear reactor system includes a reactor vessel having a barrier separating a core region from a shield region. A plurality of fuel rods containing a liquid nuclear fuel are positioned in the core region. A liquid moderator material is also positioned in the core region at least partially around the fuel rods. A plurality of heat exchangers can be positioned in the shield region, and a plurality of heat pipes can extend through the barrier. The moderator material is positioned to transfer heat received from the liquid nuclear fuel to the heat pipes, and the heat pipes are positioned to transfer heat received from the moderator material to the heat exchangers. The heat exchangers can transport the heat out of the system for use in one or more processes, such as generating electricity.

A closed-vessel molten salt reactor (cvMSR) is described herein. A cvMSR may comprise a suspended container, such as a metallic container, within a trench surrounded by a concrete enclosure and a concrete cover having a number of channels. The suspended container may be hollow and a solution of fissile materials and salt materials may be provided within the suspended container. The solution may be capable of undergoing a chain reaction nuclear fission process once a threshold temperature is reached. Heat generated by the solution may heat a fluid surrounding the suspended container. The heated fluid may be transported, through the number of channels of the concrete cover, to an external location where the heated fluid may be used in distributing heat and/or electricity generation.

A closed-vessel molten salt reactor (cvMSR) is described herein. A cvMSR may comprise a suspended container, such as a metallic container, within a trench surrounded by a concrete enclosure and a concrete cover having a number of channels. The suspended container may be hollow and a solution of fissile materials and salt materials may be provided within the suspended container. The solution may be capable of undergoing a chain reaction nuclear fission process once a threshold temperature is reached. Heat generated by the solution may heat a fluid surrounding the suspended container. The heated fluid may be transported, through the number of channels of the concrete cover, to an external location where the heated fluid may be used in distributing heat and/or electricity generation.

A combined power generation system and method of a small fluoride-salt-cooled high-temperature reactor and solar tower is provided, which belongs to the field of new energy and renewable energy application and includes: a nuclear reactor power generation system, a solar tower power generation system and a heat compensation system. Both the nuclear reactor power generation system and the solar tower power generation system adopt supercritical carbon dioxide Brayton cycle system to generate electricity efficiently; molten salt pool in the nuclear reactor power generation system stores high-temperature heat from the modular reactor, and multi-stage temperature heat is utilized for generating power and compensating heat required by the solar tower power generation system.

A combined power generation system and method of a small fluoride-salt-cooled high-temperature reactor and solar tower is provided, which belongs to the field of new energy and renewable energy application and includes: a nuclear reactor power generation system, a solar tower power generation system and a heat compensation system. Both the nuclear reactor power generation system and the solar tower power generation system adopt supercritical carbon dioxide Brayton cycle system to generate electricity efficiently; molten salt pool in the nuclear reactor power generation system stores high-temperature heat from the modular reactor, and multi-stage temperature heat is utilized for generating power and compensating heat required by the solar tower power generation system.

In various embodiments, the stabilizing face ring joint flange and assemblies thereof can be adapted to include a ring joint gasket and resist leaks when a fluid flowing through a pipe at high temperatures and pressures. The stabilizing face ring joint flange assembly with the ring grooves in each flange can be situated in such a way that once full compression is achieved on the ring groove by the gasket, raised faces of the two flanges can meet to ensure that the rotation of the pump or any potential perpendicular loading do not provide a stress on the gasket that would cause the gasket to deform or cause a seal to be lost.

In various embodiments, the stabilizing face ring joint flange and assemblies thereof can be adapted to include a ring joint gasket and resist leaks when a fluid flowing through a pipe at high temperatures and pressures. The stabilizing face ring joint flange assembly with the ring grooves in each flange can be situated in such a way that once full compression is achieved on the ring groove by the gasket, raised faces of the two flanges can meet to ensure that the rotation of the pump or any potential perpendicular loading do not provide a stress on the gasket that would cause the gasket to deform or cause a seal to be lost.

The present relates to the integration of the primary functional elements of graphite moderator and reactor vessel and/or primary heat exchangers and/or control rods into an integral molten salt nuclear reactor (IMSR). Once the design life of the IMSR is reached, for example, in the range of 3 to 10 years, it is disconnected, removed and replaced as a unit. The spent IMSR functions as the medium or long term storage of the radioactive graphite and/or heat exchangers and/or control rods and/or fuel salt contained in the vessel of the IMSR. The present also relates to a nuclear reactor that has a buffer salt surrounding the nuclear vessel. During normal operation of the nuclear reactor, the nuclear reactor operates at a temperature that is lower than the melting point of the buffer salt and the buffer salt acts as a thermal insulator. Upon loss of external cooling, the temperature of the nuclear reactor increases and melts the buffer salt, which can then transfer heat from the nuclear core to a cooled containment vessel.

The present relates to the integration of the primary functional elements of graphite moderator and reactor vessel and/or primary heat exchangers and/or control rods into an integral molten salt nuclear reactor (IMSR). Once the design life of the IMSR is reached, for example, in the range of 3 to 10 years, it is disconnected, removed and replaced as a unit. The spent IMSR functions as the medium or long term storage of the radioactive graphite and/or heat exchangers and/or control rods and/or fuel salt contained in the vessel of the IMSR. The present also relates to a nuclear reactor that has a buffer salt surrounding the nuclear vessel. During normal operation of the nuclear reactor, the nuclear reactor operates at a temperature that is lower than the melting point of the buffer salt and the buffer salt acts as a thermal insulator. Upon loss of external cooling, the temperature of the nuclear reactor increases and melts the buffer salt, which can then transfer heat from the nuclear core to a cooled containment vessel.