A passive safety system for a nuclear power plant (100) cools a nuclear power plant after shutdown (SCRAM) even when all primary water circulation has been disabled. The system comprises a source of compressed gas (112, 805) that can be its only source of operating energy, a source of water (106, 500), and a plurality of plumbing components. The system is located nearby but outside of the plant where it will not be damaged in the event of an accident inside the plant. In one embodiment, the system is located underground. In another embodiment, the system is portable so that the gas and water are carried in tanks (500, 510) on railroad cars or other wheeled conveyances. The portable system is located above ground, or optionally in a covered trench (705). In an alternative embodiment, only compressed gas is used to cool the plant.

An auxiliary system for cooling a spent nuclear fuel pool through a submersible heat exchanger to be located within the pool. In each train or installation, a single loop or series of loops of cooling fluid (e.g., sea water or service water) is circulated. The system is modular, readily and easily installed during an emergency and can be self operating with its own power source. Multiple trains may be used in parallel in order to accomplish the required degree of spent fuel pool cooling required.

An auxiliary system for cooling a spent nuclear fuel pool through a submersible heat exchanger to be located within the pool. In each train or installation, a single loop or series of loops of cooling fluid (e.g., sea water or service water) is circulated. The system is modular, readily and easily installed during an emergency and can be self operating with its own power source. Multiple trains may be used in parallel in order to accomplish the required degree of spent fuel pool cooling required.

Systems and methods for upgrading power output of previously-deployed nuclear power plants are described. Systems and methods may include a base nuclear power plant with a predetermined base power output rating and a predetermined base whole core refueling interval. Systems and methods may also include a power upgrade kit for increasing the base power output rating from the base power output rating to an increased power output rating without a change in fuel charge, reactor structures, or civil structures.

Systems and methods for upgrading power output of previously-deployed nuclear power plants are described. Systems and methods may include a base nuclear power plant with a predetermined base power output rating and a predetermined base whole core refueling interval. Systems and methods may also include a power upgrade kit for increasing the base power output rating from the base power output rating to an increased power output rating without a change in fuel charge, reactor structures, or civil structures.

A system for determining a power generated by an assembly for a nuclear reactor includes a subsystem for measuring a flow rate of a heat-transfer fluid including a body wherein the fluid flows, at least one rotor configured to be rotated by the fluid, and a device for measuring a rotation speed of the rotor. The device for measuring includes an optical module configured to transmit an incident light radiation on blades of the rotor, in a direction substantially perpendicular to an axis of rotation of the rotor, and to receive a reflected light radiation coming from the blades. The system further includes a subsystem for measuring a temperature of the fluid at an inlet and at an outlet of the assembly. The system is configured to determine the flow rate of the fluid, and to determine a power generated by the assembly.

A system for determining a power generated by an assembly for a nuclear reactor includes a subsystem for measuring a flow rate of a heat-transfer fluid including a body wherein the fluid flows, at least one rotor configured to be rotated by the fluid, and a device for measuring a rotation speed of the rotor. The device for measuring includes an optical module configured to transmit an incident light radiation on blades of the rotor, in a direction substantially perpendicular to an axis of rotation of the rotor, and to receive a reflected light radiation coming from the blades. The system further includes a subsystem for measuring a temperature of the fluid at an inlet and at an outlet of the assembly. The system is configured to determine the flow rate of the fluid, and to determine a power generated by the assembly.

Provided here is an architectural plan (the solution) for the restoration of the terminal lake, the Salton Sea, an area of prevalent geothermal sources. It includes division of the Lake into three sections, preventing pollution of the Lake from nearby farmlands and importing seawater in central section with pipeline system; providing condition for tourism, and wildlife sanctuary; generating electricity by harnessing hydro, solar, and geothermal energy; and producing potable water and lithium as byproducts. Also includes a system and method for harnessing geothermal energy for generation of electricity by using complete closed loop heat exchange systems combined with onboard drilling apparatus. The system includes several devices operating separately in many different applications in energy sectors, Also, included is alternative use for the In-Line-Pump for marine crafts propulsion.

A ventilation system for an operating space accessible to operators in a nuclear installation is intended to allow a supply of decontaminated fresh air for a period of a few hours in the event of serious accidents involving the release of radioactive activity. In particular, the component of radioactive inert gases in the fresh air supplied to the operating space should be as small as possible. For this purpose, the ventilation system has a supply air line that is guided from an external inlet to the operating space, and into which a first fan and a first inert gas adsorber column are connected. An exhaust air line is guided from the operating space to an external outlet, and into which a second fan and a second inert gas adsorber column are connected. A switching device is provided for interchanging the roles of the first and second inert gas adsorber columns.

A method and apparatus for maintaining or establishing a readiness state in a fuel cell backup system of a nuclear reactor system are disclosed. A method includes maintaining a readiness state of a fuel cell system within a set of readiness parameters, the readiness parameters a function of a characteristic of the nuclear reactor system. Another method includes monitoring a nuclear reactor system characteristic and, responsive to the monitored nuclear reactor system characteristic, establishing a readiness state of a fuel cell system. An apparatus includes a fuel cell system associated with a nuclear reactor system and a fuel cell control system configured to maintain a readiness state of the fuel cell system. Another apparatus includes a fuel cell system associated with a nuclear reactor system, a nuclear reactor characteristic monitoring system, and a fuel cell control system configured to establish a readiness state of the fuel cell system.