Abstract: A decay heat removal system for a liquid metal reactor in which a decay heat exchanger (DHX) is installed concentrically with an intermediate heat exchanger (IHX) in the same cylinder which separates the DHX and IHX from the reactor pool fluid, and serves to remove the reactor core decay heat. The cylinder surrounds the IHX and DHX, and has an open top portion protruding out of the level of the fluid in a hot pool, a bottom portion connected to a cold pool and a guide pipe for allowing the passage of the fluid from the hot pool into the IHX. The decay heat removal system can remove decay heat immediately after occurrence of an accident, thereby improving the safety of a nuclear plant.

Abstract: A direct pool cooling type passive safety grade decay heat removal method and system for removing core decay heat in a pool type liquid metal reactor when a normal heat removal system breaks down. In the liquid metal reactor comprising a reactor vessel, the interior of which is partitioned into a hot pool above a core and a cold pool around the core so that liquid level difference between the hot pool and the cold pool is maintained by a primary pumping head under normal steady-state conditions, is disposed at least one circular vertical tube in such a manner that the sodium in the circular vertical tube is maintained with the same liquid level as the liquid level of the sodium in the cold pool.

Abstract: A decay heat removal system for a liquid metal reactor in which a decay heat exchanger (DHX) is installed concentrically with an intermediate heat exchanger (IHX) in the same cylinder which separates the DHX and IHX from the reactor pool fluid, and serves to remove the reactor core decay heat. The cylinder surrounds the IHX and DHX, and has an open top portion protruding out of the level of the fluid in a hot pool, a bottom portion connected to a cold pool and a guide pipe for allowing the passage of the fluid from the hot pool into the IHX. The decay heat removal system can remove decay heat immediately after occurrence of an accident, thereby improving the safety of a nuclear plant.

Abstract: A decay heat removal system for a liquid metal reactor, in which a decay heat exchanger (DHX) is installed concentrically with an intermediate heat-exchanger (IHX) in the same cylinder which separates the DHX and IHX from the reactor pool fluid, and serves to remove the reactor core decay heat. The cylinder surrounds the IHX and the DHX, and has an opened top portion protruded out of the level of the fluid in a hot pool, a bottom portion connected to a cold pool and a guide pipe for allowing the passage of the fluid from the hot pool into the IHX. The decay heat removal system can remove decay heat immediately after occurrence of an accident, thereby improves the safety of a nuclear plant.

Abstract: Dis0closed herein is a direct pool cooling type passive safety grade decay heat removal method and system for removing core decay heat in a pool type liquid metal reactor when a normal heat removal system breaks down. In the liquid metal reactor comprising a reactor vessel, the interior of which is partitioned into a hot pool above a core and a cold pool around the core so that liquid level difference between the hot pool and the cold pool is maintained by a primary pumping head under normal steady-state conditions, is disposed at least one circular vertical tube in such a manner that the sodium in the circular vertical tube is maintained with the same liquid level as the liquid level of the sodium in the cold pool.

Abstract: Disclosed herein is a steam generator for a liquid metal reactor and a heat transfer method thereof, and more particularly a steam generator for a liquid metal reactor having intermediate fluid forcibly circulated therein and structurally improved coiled heat transfer tubes installed therein, and a heat transfer method of such a steam generator, whereby an accident of the sodium-water reaction is practically prevented and heat transfer efficiency is improved. The heat transfer method of the steam generator for the liquid metal reactor including a reactor core, a steam generator, and a turbine, utilizes forced circulation for the intermediate fluid in the steam generator. The forced circulation is carried out through a flow channel defined in the steam generator, which forms a closed flow circuit for the intermediate fluid, by means of operation of a circulation pump installed in the flow channel.

Abstract: Disclosed herein is a steam generator for a liquid metal reactor and a heat transfer method thereof, and more particularly a steam generator for a liquid metal reactor having intermediate fluid forcibly circulated therein and structurally improved coiled heat transfer tubes installed therein, and a heat transfer method of such a steam generator, whereby an accident of the sodium-water reaction is practically prevented and heat transfer efficiency is improved.

Abstract: A method and device for removing decay heat from a liquid metal reactor using a thermosyphon so as to cool the reactor is disclosed. The method and device of this invention uses a thermosyphon heating part in place of a conventional air separator, thus improving its decay heat removal capacity. In the method of this invention, decay heat from the reactor is absorbed at the flowing air and additionally at the evaporator section of the thermosyphon. The absorbed heat at the evaporator section is, thereafter, dissipated to the atmosphere from the condenser section of the thermosyphon. In the liquid metal reactor installed at a position between a containment and a reactor support concrete wall, the thermosyphon is installed at a position between the concrete wall and the containment vessel.