Korea Atomic Energy Research Institute

Suhn Choi

Young In Kim

Keung Koo Kim

Hun Sik Han

Ju Hyeon Yoon

Jae Joo Ha

Young Min Bae

Soo Jai Shin

Joo Hyung Moon

Kyung Jun Kang

Cheon Tae Park

Tae-Wan Kim

Han Ok Kang

Seung Yeob Ryu

Jong-Wook Kim

Sung Jae Yi

Dae Hyun Hwang

Jae-Seon Lee

Keung-Koo Kim

Jong In Kim

The present invention relates to a plate heat exchanger and provides a heat exchanger and a nuclear power plant comprising same, the heat exchanger comprising: a plate unit having multiple plates overlapping one another; a flow path unit, which forms flow paths having fluids flowing therein by processing at least parts of the respective plates; and a detection flow path formed between the multiple plates so as to allow the fluids leaking from the flow paths to flow thereinto and formed so as to detect the leakage of the fluids from the flow paths.

Heat exchanger and nuclear power plant comprising same

Disclosed is a nuclear power plant which drives a Stirling engine by means of heat generated in nuclear power plant safety systems during an accident, uses the resulting power directly or generates electric power so as to supply the power to the safety systems, and thus can improve economic efficiency as well as the reliability of safety systems, such as a passive safety system, by operating the safety systems without an emergency diesel generator or external electric power.

Nuclear power plant

A passive safety system comprises a heat exchanger, a thermoelectric element, and a fan unit. The heat exchanger is located inside a containment. The heat exchanger allows for temperature of atmosphere in the containment to be reduced. The thermoelectric element is disposed within the heat exchanger. The thermoelectric element is configured to generate electricity due to a temperature difference. The fan unit receives electricity generated by the thermoelectric element. The fan unit is configured to increase flow rate of fluid inside the containment. A nuclear power plant can include the passive safety system.

Passive safety system and nuclear power plant comprising same

The present invention provides passive safety equipment, comprising: a cooling part formed to cool a first fluid, which is emitted from a reactor coolant system or a steam generator, and a second fluid in a housing; and a circulation induction sprayer which is formed to spray the first fluid emitted from the reactor coolant system or the steam generator into the cooling part, has at least part thereof open to the inside of the housing such that the second fluid flows thereinto according to a drop in pressure caused by the spraying of the first fluid, and sprays the second fluid with the inflown first fluid.

Passive safety equipment for a nuclear power plant

The present invention provides a facility for reducing radioactive material comprising: a cooling water storage unit installed inside a containment and formed to store cooling water; a boundary unit forming a boundary of radioactive material inside the containment and surrounding a reactor coolant system installed inside the containment to prevent a radioactive material from releasing from the reactor coolant system or a pipe connected with the reactor coolant system to the containment; a connecting pipe connected with an inner space of the boundary unit and the cooling water storage unit to guide a flow of a fluid caused by a pressure difference between the boundary unit and the cooling water storage unit from the boundary unit to the cooling water storage unit; and a sparging unit disposed to be submerged in the cooling water stored in the cooling water storage unit and connected with the connecting pipe to sparge the fluid that has passed through the connecting pipe and the radioactive material contained in the fluid to the cooling water storage unit.

Facility for reducing radioactive material and nuclear power plant having the same

Disclosed is a control rod drive mechanism. More specifically, the control rod drive mechanism includes a guide memberdisposed in a nuclear reactor to receiving a drive shaft; a latch assemblydisposed in the guide memberto enable the drive shaftto be withdrawn and inserted; a supporting memberconnected to the guide memberto cover the drive shaftand to support the latch assembly; and a plurality of coil housingsspaced apart and connected to the guide memberto cover the latch assembly, and each having a coilbuilt therein.

Control rod drive mechanism built in nuclear reactor

Growing community of inventors

Daejeon, South Korea

Suhn Choi