A method, system, and apparatus for the thermal storage of nuclear reactor generated energy including diverting a selected portion of energy from a portion of a nuclear reactor system to an auxiliary thermal reservoir and, responsive to a shutdown event, supplying a portion of the diverted selected portion of energy to an energy conversion system of the nuclear reactor system.

A method, system, and apparatus for the thermal storage of nuclear reactor generated energy including diverting a selected portion of energy from a portion of a nuclear reactor system to an auxiliary thermal reservoir and, responsive to a shutdown event, supplying a portion of the diverted selected portion of energy to an energy conversion system of the nuclear reactor system.

A method for decommissioning a nuclear facility includes: floating a nuclear reactor pressure vessel above a cavity; positioning a mounting device on bio-protective concrete to cover the cavity with the mounting device; mounting a lower portion of the nuclear reactor pressure vessel on the mounting device; and cutting and decommissioning the nuclear reactor pressure vessel mounted on the mounting device.

A transportable nuclear power generator assembly includes a first modular nuclear power generator unit and a second nuclear power generator unit. The first modular nuclear power generator unit includes a first transport container, a first nuclear power module positioned inside the first transport container, and a first supporting mechanism movably supports the first nuclear power module inside the first transport container. The second modular nuclear power generator unit includes a second transport container, a second nuclear power module positioned inside the second transport container, and a second supporting mechanism configured to support the second nuclear power module inside the second transport container. At least one of the first supporting mechanism and the second supporting mechanism is configured to move at least one of the first nuclear power module and the second nuclear power module relative to one another to result in an at least critical state or a subcritical state.

A transportable nuclear power generator assembly includes a first modular nuclear power generator unit and a second nuclear power generator unit. The first modular nuclear power generator unit includes a first transport container, a first nuclear power module positioned inside the first transport container, and a first supporting mechanism movably supports the first nuclear power module inside the first transport container. The second modular nuclear power generator unit includes a second transport container, a second nuclear power module positioned inside the second transport container, and a second supporting mechanism configured to support the second nuclear power module inside the second transport container. At least one of the first supporting mechanism and the second supporting mechanism is configured to move at least one of the first nuclear power module and the second nuclear power module relative to one another to result in an at least critical state or a subcritical state.

The present disclosure relates to an L-shaped header of a steam generator including a spiral heat transfer tube, and a coupling structure between the L-shaped header and the heat transfer tube, wherein an upper end and a lower end of a heat transfer tube assembly configured with a plurality of heat transfer tubes are vertically formed, and the upper and lower ends of the heat transfer tube assembly are vertically coupled to a bottom side or a top side of the header. Therefore, the heat transfer tubes constituting the same concentric circle may use the heat transfer tubes formed with the same shape, thereby improving the manufacturability of parts and reducing the manufacturing cost.

The present disclosure relates to an L-shaped header of a steam generator including a spiral heat transfer tube, and a coupling structure between the L-shaped header and the heat transfer tube, wherein an upper end and a lower end of a heat transfer tube assembly configured with a plurality of heat transfer tubes are vertically formed, and the upper and lower ends of the heat transfer tube assembly are vertically coupled to a bottom side or a top side of the header. Therefore, the heat transfer tubes constituting the same concentric circle may use the heat transfer tubes formed with the same shape, thereby improving the manufacturability of parts and reducing the manufacturing cost.

A nuclear reactor is positioned on a barge which floats on the water of a water tank. The water tank includes a bottom wall, first and second end walls and first and second side walls. The bottom wall includes a lower layer of concrete, an intermediate layer of water impervious material positioned on the lower layer of concrete, and an upper layer of concrete positioned on the intermediate layer of water impervious material. Each of the first and second end walls and the first and second side walls includes an outer layer of concrete, an intermediate layer of water impervious material positioned at the inner side of the outer layer of concrete, and an inner layer of concrete material positioned at the inner side of the intermediate layer of water impervious material.

One variation of a method for deploying a nuclear reactor system includes: constructing a tunnel at a particular location; and installing the nuclear reactor, loaded with a first core assembly, within the tunnel. The method further includes, during an operating period: in response to detecting a high-energy demand period: triggering operation of the nuclear reactor at a first capacity, directing a first portion of energy output to a charging station for charging electric vehicles, and directing a second portion, less than the first portion, of energy output to a gas sequestration subsystem; and, in response to detecting a low-energy demand period, triggering operation of the nuclear reactor at a second capacity less than the first capacity, directing a third portion of energy, less than the first portion, output to the charging station, and directing a fourth portion of energy, exceeding the second portion, output to the gas sequestration subsystem.

A method for decommissioning a nuclear facility includes: floating the nuclear reactor pressure vessel above the cavity; rotating the reactor pressure vessel so that the upper portion of the nuclear reactor pressure vessel is closer to the bio-protective concrete than the lower portion; mounting the upper portion of the nuclear reactor pressure vessel on the neighboring upper surface of the bio-protective concrete; and cutting and decommissioning the nuclear reactor pressure vessel mounted on the neighboring upper surface.