An apparatus includes a reactor core with one or more heat pipes passing through in an x-direction, one or more heat pipes passing through in a y-direction, and one or more heat pipes passing through in a z-direction. The one or more heat pipes passing through in the z-direction are pumped heat pipes.

The invention relates to nuclear power engineering and is intended for using in power plants with a reactor with a heavy liquid metal coolant (HLMC) based on lead or on lead-bismuth alloys.

The invention makes it possible to increase the radiation protection efficiency for the in-vessel equipment of a nuclear reactor, to increase the heat storage capacity of the primary circuit, to reduce the nuclear reactor weight, and to improve its strength characteristics.

In the in-vessel space of a nuclear reactor, which is not occupied by the necessary equipment, containers filled with a material that reflects or absorbs neutrons, with a heat capacity greater than that of the coolant, are installed with gaps ensuring the coolant flow, while the containers are placed in such a way that the resulting gaps form channels with a turbulent coolant flow to cool these containers at a flow rate corresponding to the nominal power output level of the nuclear reactor.

Piping loops can carry either forced or natural circulation coolant flow from and back to a nuclear reactor depending on reactor and coolant state, and can transition between the two. The loop flows into a heat exchanger that cools the coolant and may even condense the coolant. The heat exchanger can drive natural circulation coolant flow, and a pump on the loop can drive forced circulation. Coolant direction may be reversed through the heat exchanger in different modes. Loops may be installed directly on existing isolation condenser systems or come off of a primary loop generating electricity commercially. Actuation valves may isolate and actuate the system merely by disallowing or allowing coolant flow. Different flow modes and coolant direction may be similarly achieved by pump actuation and/or valve opening/closing. Beyond the pump and simple valve actuation, loops may be entirely passive.

Controlled-debris elements inhibit the formation of a fibrous/particulate debris bed that unduly increases the pressure head loss through the perforated plates of strainers in a nuclear power plant emergency core cooling system. In a loss of cooling accident, pumps draw cooling water through the plates, which retain on their surfaces fibrous material in the circulating water to prevent it from reaching the pumps while permitting entrained particulate matter to pass through the perforations. The controlled-debris elements have a specific gravity substantially the same as the circulating water so they are entrained in the cooling water that is drawn toward the strainers and intimately intermix with the fibrous and particulate matter in the cooling water. The elements are configured to provide open structures in the bed formed on the plate surfaces to distribute fibers in the flow away from the surface and maintain cavities between the elements for the particulates.

A passive safety system for removing decay heat from a nuclear power system may comprise a shroud structure and a heat generator that is within the shroud structure. A thermoelectric device may be disposed in thermal contact with the heat generator. The thermoelectric device is configured to generate a voltage based on a temperature difference between opposite parts of the thermoelectric device. A fan arrangement is disposed above the heat generator and in electrical connection with the thermoelectric device. The fan arrangement is configured to increase a coolant flow through the coolant passage to the outlet opening based on the voltage from the thermoelectric device.

A generator is installed on and provides electrical power from a turbine by converting the turbine's mechanical energy to electricity. The generated electrical power is used to power controls of the turbine so that the turbine can remain in use through its own energy. The turbine can be a safety-related turbine in a nuclear power plant, such that, through the generator, loss of plant power will not result in loss of use of the turbine and safety-related functions powered by the same. Appropriate circuitry and electrical connections condition the generator to work in tandem with any other power sources present, while providing electrical power with properties required to safely power the controls.

The present invention discloses a nuclear reactor coolant pump that does not rely on an electric motor, but is operated by means of driving force generated inside a nuclear power plant, so a to be capable of maintaining the safety of the nuclear reactor when the nuclear reactor is operating normally and also in the event of an accident in the nuclear reactor. The nuclear reactor coolant pump comprises: a pump impeller rotatably installed in a first fluid passage of a nuclear reactor coolant system to circulate a first fluid inside the nuclear reactor coolant system; a drive unit receiving steam from a steam generator to generate driving force to rotate the pump impeller, and rotating about the same rotating shaft as the pump impeller to transfer the generated driving force to the pump impeller; and a steam supplying unit forming a passage between the steam generator and the drive unit to supply at least a portion of the steam released from the steam generator to the drive unit.

A nuclear steam supply system having a shutdown system for removing residual decay heat generated by a nuclear fuel core. The steam supply system may utilize gravity-driven primary coolant circulation through hydraulically interconnected reactor and steam generating vessels forming the steam supply system. The shutdown system may comprise primary and secondary coolant systems. The primary coolant cooling system may include a jet pump comprising an injection nozzle disposed inside the steam generating vessel. A portion of the circulating primary coolant is extracted, pressurized and returned to the steam generating vessel to induce coolant circulation under reactor shutdown conditions. The extracted primary coolant may further be cooled before return to the steam generating vessel in some operating modes. The secondary coolant cooling system includes a pumped and cooled flow circuit operating to circulate and cool the secondary coolant, which in turn extracts heat from and cools the primary coolant.

Supports with integrated sensors for nuclear reactor steam generators, and associated systems and methods, are disclosed. A representative method for forming a nuclear-powered steam generator includes forming an instrumented support, the instrumented support including a carrier portion and a retainer portion, with at least one of the carrier portion or the retainer portion being integrally formed with a sensor via an additive manufacturing process. The method can further include coupling the sensor to a communication link, supporting a helical steam conduit on the instrumented support, and installing the helical steam conduit and the instrumented support in a nuclear reactor. The helical steam conduit is positioned along a primary flow path, which is in turn positioned to circulate a heated primary flow in thermal communication with the helical steam conduit.

A passive safe cooling system includes a water replenishing tank, an advanced safe injection tank, a built-in material replacing water tank, a pressure relief system, a passive emergency water supply system and a passive containment cooling system, the passive emergency water supply system is adapted for hermetically running through the containment and is configured correspondingly to a steam generator in the containment, and the passive containment cooling system is adapted for hermetically running through the containment to remove the heat from the containment. This system can effectively implement safety functions such as nuclear core reactivity control, residual heat removal and containment of radioactive material under a nuclear accident, ensure the reactor core to be effectively cooled down and maintain in a safe shutdown state, improve the safety of the nuclear power plant and greatly reduce the construction costs and operation and maintenance costs.