Korea Atomic Energy Research Institute

King Abdullah City for Atomic and Renewable Energy

Juhyeon Yoon

Seok Koo Kim

Young In Kim

Youngin Kim

Joohyung Moon

Seungyeob Ryu

Soojai Shin

Hyunjun Cho

Hunsik Han

Youngmin Bae

Cheongbong Chang

Junewoo Kee

Minkyu Lee

Hyungi Yoon

Kilsung Kwon

The present invention relates to a prevention device for loss of coolant accident (LOCA) and a nuclear reactor having the same. The prevention device for LOCA includes a nozzle portion integrally formed in a reactor vessel and having a communication hole communicating with the inside of the reactor vessel, a nozzle finishing portion assembled to the nozzle portion and an injection line for injecting a fluid to the inside of the reactor vessel respectively on both sides thereof in a communicating manner, and a check valve mounting portion installed to be embedded inside the nozzle portion and having at least one check valve opened by flow such that the fluid is injected into the reactor vessel, wherein the check valve blocks outflow of a reactor coolant from the reactor vessel in case of failure of the injection line.

Prevention device for LOCA and nuclear reactor having the same

A heat exchanger for a steam generator according to one embodiment of the present invention comprises a plate and channels formed on the plate by an photo-chemical etching method, wherein the channels comprise: a primary heat transmission section formed in a manner of having a bent or curved flow path so as to be extended longer than the length at which one side and the other side are connected in a straight line; and a flow path resistance section, formed having a smaller width than the width of the channels formed on the primary heat transmission section and being connected to the one side of the primary transmission section in a manner of having a bent or curved flow path so as to be extended longer than the length at which an inlet and an outlet are connected in a straight line.

Heat exchanger for steam generator and steam generator comprising same

An in-vessel cooling and power generation system according to the present disclosure may include a small scale reactor vessel, a heat exchange section provided inside the reactor vessel, and formed to supply supercritical fluid to receive heat from a reactor coolant system in the reactor vessel, an electric power production section comprising a supercritical turbine formed to produce electric energy using the energy of the supercritical fluid whose temperature has increased while receiving heat from the reactor coolant system, a cooling section configured to exchange heat with the supercritical fluid discharged after driving the supercritical turbine to shrink a volume of the supercritical fluid, wherein the supercritical fluid that has received heat from the reactor coolant system in the heat exchange section is formed to circulate through the electric power production section, and the cooling section.

Cooling facility in a reactor vessel and electric power generation system

Growing community of inventors

Daejeon, South Korea

Juhyeon Yoon