Systems and methods for refueling a nuclear reactor that has a reactor core in a reactor pool having a plurality of elongated reactor core components, a fuel pool for storing core components, and a transfer channel connecting the fuel pool to the reactor pool. The method includes retrieving a replacement core component from the fuel pool, and securing the replacement core component in a first compartment of a handover assembly in a vertical position. The method also includes retrieving a spent core component from the reactor core, and securing the spent core component in a second compartment of the handover assembly in a vertical position. The replacement core component is retrieved from the first compartment and installed into the reactor core. The spent core component is retrieved from the second compartment and stored in a storage rack in the fuel pool.

Systems and methods for refueling a nuclear reactor that has a reactor core in a reactor pool having a plurality of elongated reactor core components, a fuel pool for storing core components, and a transfer channel connecting the fuel pool to the reactor pool. The method includes retrieving a replacement core component from the fuel pool, and securing the replacement core component in a first compartment of a handover assembly in a vertical position. The method also includes retrieving a spent core component from the reactor core, and securing the spent core component in a second compartment of the handover assembly in a vertical position. The replacement core component is retrieved from the first compartment and installed into the reactor core. The spent core component is retrieved from the second compartment and stored in a storage rack in the fuel pool.

A modular nuclear reactor system includes a lift-out, replaceable nuclear reactor core configured for replacement as a singular unit during a single lift-out event, such as rather than lifting and replacing individual fuel assemblies and/or fuel elements. The system includes a reactor vessel and a power generation system configured to convert thermal energy in a high temperature working fluid received from the reactor vessel into electrical energy. The reactor vessel includes: a vessel inlet and an adjacent vessel outlet arranged near a bottom on the vessel; a vessel receptacle configured to receive a unified core assembly; locating datums in the base of the vessel receptacle and configured to constrain a core assembly in multiple degrees of freedom; and an interstitial zone surrounding the vessel receptacle and housing a set of control or moderating drums.

A modular nuclear reactor system includes a lift-out, replaceable nuclear reactor core configured for replacement as a singular unit during a single lift-out event, such as rather than lifting and replacing individual fuel assemblies and/or fuel elements. The system includes a reactor vessel and a power generation system configured to convert thermal energy in a high temperature working fluid received from the reactor vessel into electrical energy. The reactor vessel includes: a vessel inlet and an adjacent vessel outlet arranged near a bottom on the vessel; a vessel receptacle configured to receive a unified core assembly; locating datums in the base of the vessel receptacle and configured to constrain a core assembly in multiple degrees of freedom; and an interstitial zone surrounding the vessel receptacle and housing a set of control or moderating drums.

An in-core instrumentation system for a reactor module includes a plurality of in-core instruments connected to a containment vessel and a reactor pressure vessel at least partially located within the containment vessel. A reactor core is housed within a lower head that is removably attached to the reactor pressure vessel, and lower ends of the in-core instruments are located within the reactor core. The in-core instruments are configured such that the lower ends are concurrently removed from the reactor core as a result of removing the lower head from the reactor pressure vessel.

An in-core instrumentation system for a reactor module includes a plurality of in-core instruments connected to a containment vessel and a reactor pressure vessel at least partially located within the containment vessel. A reactor core is housed within a lower head that is removably attached to the reactor pressure vessel, and lower ends of the in-core instruments are located within the reactor core. The in-core instruments are configured such that the lower ends are concurrently removed from the reactor core as a result of removing the lower head from the reactor pressure vessel.

The present disclosure provides a lifting device for lifting a closure head assembly from a reactor vessel body in a nuclear power generation system. The lifting device comprises at least one lifting element having an engagement surface configured to engage an underside surface of the closure head assembly. The at least one lifting element is axially adjustable in height between a retracted position in which its axial height is such that the closure head assembly seals against the body of the reactor vessel and an extended position in which its axial height is such that the closure head assembly is raised above the body of the reactor vessel.

The present disclosure provides a refuelling device for lifting a fuel rod assembly from a reactor core of a nuclear power generation system in a deployment location and transporting it to a storage location. The refuelling device comprises a device body having an open base and defining a chamber for housing a coolant. A sealing plate is movable between an open position in which the chamber is open and a closed position in which the chamber is sealed. The device further comprises a shielding element formed of radioactive shielding material and moveably mounted within the chamber. It has a storage cavity having an open lower end, the shielding element being movable between a retracted position in which it is fully contained within the chamber and an extended position in which it extends from the chamber through the open base of the device body. The device further comprises a rod lifting system having a rod connector for releasable connection to the fuel rod assembly and configured to raise the fuel rod assembly to within the storage cavity when the device is in the deployment location, the sealing plate is in the open position and the shielding element is in its extended position.

In the present invention, a nuclear power plant using U235 as nuclear fuel is converted into a nuclear power plant that uses spent nuclear fuel rods as the Nt source and that uses Th as nuclear fuel. The nuclear power plant using U235 as nuclear fuel is converted into a nuclear power plant using Th as nuclear fuel.

In the present invention, a nuclear power plant using U235 as nuclear fuel is converted into a nuclear power plant that uses spent nuclear fuel rods as the Nt source and that uses Th as nuclear fuel. The nuclear power plant using U235 as nuclear fuel is converted into a nuclear power plant using Th as nuclear fuel.