Abstract: A nuclear reactor system for generating electricity includes a nuclear reactor that uses water as a coolant and a moderator, and generates thermal energy through nuclear fission. The reactor includes a reactor vessel and a reactor core. The reactor core comprises a plurality of fuel assemblies and one or more core baffles. In an embodiment the reactor core is square-shaped with a hollow center portion, and is concentric with the reactor vessel. The reactor permits decay-heat removal from the fuel assemblies in the absence of the coolant. A power conversion system is arranged to indirectly receive thermal energy generated by the reactor core and to generate electricity. A refueling water storage tank is useable when the reactor core is refueled with nuclear fuel. A containment surrounds the reactor vessel and the refueling water storage tank.

Abstract: An emergency core cooling system removes decay heat generated by a reactor core of a reactor system. A reactor vessel uses water as a coolant. A containment structure surrounds the reactor system. A reactor cavity surrounds the reactor vessel. A first cavity pipe extends into the reactor vessel and provides a recirculation loop of cooling water by discharging vapor generated in the reactor vessel and supplying condensed water collected in the reactor cavity in an opposite direction.

Abstract: The present invention relates to the in-vessel and ex-vessel melt cooling system having the core catcher. This system includes a reactor vessel having the core inside of the vessel, a core catcher that can cool the core melt ejecting from the damaged reactor vessel, a reactor cavity including the reactor vessel and the core catcher, IRWST (In-Containment Refueling Water Storage Tank) that can supply cooling water to the reactor cavity, and a control unit that can cut out the cooling water supply when the reactor cavity is filled with cooling water to the required level.

Abstract: The present invention relates to a public acceptable simple water-cooled reactor system for generating electricity and, more particularly, to a public acceptable simple water-cooled reactor system for generating electricity, which includes: a water-cooled reactor that uses water as a coolant and a moderator and generates thermal energy through nuclear fission; a power conversion system that is connected to the water-cooled reactor so as to indirectly receive the thermal energy generated by the reactor core of the water-cooled reactor via a heat exchanger in a containment and generate electricity; a in-containment refueling water storage tank that is used when the water-cooled reactor is refueled with a nuclear fuel; and a containment that surrounds the entire reactor system including the water-cooled reactor and the in-containment refueling water storage tank.

Abstract: An emergency core cooling system and method for a fail-safe water-cooled reactor is disclosed, which completely remove decay heat generated from a core in safety without the use of an active component (i.e., pump). The exemplary embodiments include a reactor vessel using water as a coolant and a moderator, and receiving therein a reactor core on which nuclear fission occurs; a containment surrounding the entire reactor system including the reactor vessel and condensing a vapor discharged from the reactor vessel when emergency core cooling is performed; a reactor cavity which surrounds the reactor vessel and in which water condensed in the containment is collected due to gravity; a first cavity pipe provided to pass through the reactor vessel; and a cavity valve provided on the cavity pipe to open the first cavity pipe when emergency core cooling is performed and discharge the vapor generated from the reactor vessel.

Abstract: Disclosed herein is an integrated process for production of electricity, hydrogen, and water using a high-temperature gas-cooled reactor as a single source, comprising: the high-temperature gas-cooled reactor, a power conversion unit connected directly or indirectly with the high-temperature gas-cooled reactor to receive heat produced by a reactor core of the high-temperature gas-cooled reactor and drive a gas turbine by the heat, thereby producing electricity through an electric generator, a hydrogen production unit that produces hydrogen by receiving the heat produced by the high-temperature gas-cooled reactor and/or the electricity produced by the electric generator, an electrical desalination unit that produces water by using the electricity produced by the electric generator, and a thermal desalination unit that produces water by distilling fresh water from salt water with waste heat recovered from a precooler and an intercooler of the power conversion unit.

Abstract: Disclosed herein is an iodine-sulfur cycle for nuclear hydrogen production, which can improve thermochemical efficiency.

Abstract: Disclosed herein is an integrated process for production of electricity, hydrogen, and water using a high-temperature gas-cooled reactor as a single source, including: the high-temperature gas-cooled reactor, a power conversion unit connected directly or indirectly with the high-temperature gas-cooled reactor to receive heat produced by a reactor core of the high-temperature gas-cooled reactor and drive a gas turbine by the heat, thereby producing electricity through an electric generator, a hydrogen production unit that produces hydrogen by receiving the heat produced by the high-temperature gas-cooled reactor and/or the electricity produced by the electric generator, an electrical desalination unit that produces water by using the electricity produced by the electric generator, and a thermal desalination unit that produces water by distilling fresh water from salt water with waste heat recovered from a precooler and an intercooler of the power conversion unit.

Abstract: A passive containment cooling system for a nuclear reactor and a method of cooling a pressurized water reactor thereby has an isolation condensing means for cooling and condensing steam and accumulating and cooling noncondensable gas released from within a containment of a nuclear reactor. A steam-driven air ejector which is driven by steam of high temperature and pressure generated from a steam generator is used to exhaust the noncondensable gas from the isolation condensing means, to flow the noncondensable gas into the containment. A steam generator makeup water storage tank makes up the water inventory of the steam generator and provides security for steam generator water inventory lost by operation of the steam-driven air ejector. This leads to the removal of early decay heat by dumping steam from the steam generator into the tank and injection of makeup water into the steam generator during the early stage of an accident.