Korea Atomic Energy Research Institute

Korea Hydro Nuclear Power Co., Ltd.

Yoon Sub Sim

Seong O Kim

Won Dae Jeon

Seong-O Kim

Do Hee Hahn

Eui Kwang Kim

Myung Hwan Wi

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.

Decay heat removal system for liquid metal reactor

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.

Stable and passive decay heat removal system for liquid metal reactor

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. By the provision of the heat transfer method of the present invention characterized by intermediate fluid forcibly circulated therein and structurally improved coiled heat transfer tubes installed therein, an accident of the sodium-water reaction is practically prevented and heat transfer efficiency is improved. Furthermore, the steam generator is easily installed inside a containment dome, and an intermediate heat transport system and a mitigating system against a sodium-water reaction accident are eliminated from the liquid metal reactor.

Steam generator for liquid metal reactor and heat transfer method thereof

Growing community of inventors

Daejeon, South Korea

Yoon Sub Sim