Korea Atomic Energy Research Institute

King Abdullah City for Atomic and Renewable Energy

Joohyung Moon

Youngin Kim

Seok Koo Kim

Seungyeob Ryu

Soojai Shin

Hyunjun Cho

Juhyeon Yoon

Cheongbong Chang

Hunsik Han

Youngmin Bae

Junewoo Kee

Minkyu Lee

Hyungi Yoon

Bonghyun Cho

Keungkoo Kim

Kilsung Kwon

Myungjun Kim

Heejoon Lee

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 safety injection device includes, a cooling water storage section accommodating cooling water injected into the reactor coolant system, a power producing section producing power with steam discharged from the reactor coolant system in case of an accident, a steam supply pipe transmitting steam discharged from the reactor coolant system to the power producing section, a steam discharge pipe discharging steam used to drive the power producing section and a safety injection line supplying cooling water accommodated in the cooling water storage section to the inside of the reactor coolant system. In addition, cooling water accommodated in the cooling water storage section is supplied to the inside of the reactor coolant system, based on the power produced by the power producing section, through a cooling water inlet pipe connecting the cooling water storage section and the power producing section.

Cooling water safety injection device powered by steam discharged during an accident and nuclear power plant having the 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

Provided is a device for measuring a micro flow rate. The device includes a container having an internal space for containing a fluid flowing therein and an inflow line and an outflow line formed in communication with the internal space, a fluid level gauge configured to sense whether a level of a fluid collected in the container rises to a predetermined height to conduct or block flow of an electric current, a control valve disposed in the outflow line and configured to open or close the outflow line according to a state in which the control valve is electrically connected to or disconnected from the fluid level gauge such that the outflow line is opened or closed according to a change in the fluid level; and a control unit configured to calculate a micro flow rate of the fluid collected in the container using information acquired from at least one of the fluid level gauge and the control valve.

Measuring device for micro flow rate and nuclear power plant having the same

Growing community of inventors

Daejeon, South Korea

Joohyung Moon